C26.02 - Fuel and Fertile Material Specifications

ABSTRACT
This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
SCOPE
1.1 This specification covers finished sintered and ground (U, Pu)O2 pellets for use in light water reactors. It applies to (U, Pu)O2 pellets containing a plutonium mass fraction up to 15 % (that is, mass of Pu divided by the sum of masses U, Pu, and Am yielding 0.15 or less).  
1.2 Pellets produced under this specification are available in four grades.  
1.2.1 Grade R—240Pu / (Pu + Am) isotope mass fraction is at least 19 %.  
1.2.2 Grade F—240Pu / (Pu + Am) isotope mass fraction is at least 7 % and less than 19 %.  
1.2.3 Grade N1—240Pu / (Pu + Am) isotope mass fraction is less than 7 %.  
1.2.4 Grade N2—240Pu /239Pu isotope mass fraction does not exceed 0.10 (10 %).  
1.3 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50—Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71—Packaging and Transportation of Radioactive Material; and Code of Federal Regulations Title 49, Part 173—General Requirements for Shipments and Packaging.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 The following safety hazards caveat pertains only to the technical requirements portion, Section 4, of this specification: This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technic...

SIGNIFICANCE AND USE
5.1 Uranium hexafluoride is normally produced and handled in large (typically 1 to 14-ton) quantities and must, therefore, be characterized by reference to representative samples (see ISO 7195). The samples are used to determine compliance with the applicable commercial specification C787. The quantities involved, physical properties, chemical reactivity, and hazardous nature of UF6 are such that for representative sampling, specially designed equipment must be used and operated in accordance with the most carefully controlled and stringent procedures. This practice can be used by UF6 converters to review the effectiveness of existing procedures or as a guide to the design of equipment and procedures for future use.  
5.2 The intention of this practice is to avoid liquid UF6 sampling once the cylinder has been filled. For safety reasons, manipulation of large quantities of liquid UF6 should be avoided when possible.  
5.3 It is emphasized that this practice is not meant to address conventional or nuclear criticality safety issues.
SCOPE
1.1 This practice covers methods for withdrawing representative sample(s) of uranium hexafluoride (UF6) during a transfer occurring in the gas phase. Such transfer in the gas phase can take place during the filling of a cylinder during a continuous production process, for example the distillation column in a conversion facility. Such sample(s) may be used for determining compliance with the applicable commercial specification, for example Specification C787.  
1.2 Since UF6 sampling is taken during the filling process, this practice does not address any special additional arrangements that may be agreed upon between the buyer and the seller when the sampled bulk material is being added to residues already present in a container (“heels recycle”). Such arrangements will be based on QA procedures such as traceability of cylinder origin (to prevent for example contamination with irradiated material).  
1.3 If the receiving cylinder is purged after filling and sampling, special verifications must be performed by the user to verify the representativity of the sample(s). It is then expected that the results found on volatile impurities with gas phase sampling may be conservative.  
1.4 This practice is only applicable when the transfer occurs in the gas phase. When the transfer is performed in the liquid phase, Practice C1052 should apply. This practice does not apply to gas sampling after the cylinder has been filled since the sample taken will not be representative of the cylinder.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification covers sintered uranium dioxide pellets containing 235U for use in nuclear reactors. Chemical requirements include uranium content, impurity content, stoichiometry, and moisture content. Maximum concentration limits are specified for impurity elements such as: aluminum, carbon, calcium+magnesium, chlorine, chromium, cobalt, fluorine, hydrogen, iron, nickel, nitrogen, silicon, and thorium. Chemical analyses shall be performed. Nuclear requirements include isotopic content and equivalent boron content. The following are physical characteristics of the material: dimensions, pellet density, grain size and pore morphology, pellet integrity –
SCOPE
1.1 This specification is for finished sintered UO2 pellets. It applies to UO2 pellets containing uranium (U) of any  235U concentration for use in nuclear reactors.  
1.2 This specification recognizes the presence of reprocessed U in the fuel cycle and consequently defines isotopic limits for UO2 pellets made from commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unirradiated U. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.  
1.3 This specification does not include (a) provisions for preventing criticality accidents, (b) requirements for health and safety, (c) avoidance of hazards, or (d) shipping precautions and controls. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. Examples of U.S. Government documents are Code of Federal Regulations (Latest Edition), Title 10, Part 50, Title 10, Part 70, Title 10, Part 71, and Title 49, Part 173.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 The following precautionary caveat pertains only to the technical requirements portion, Section 4, of this specification:  This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability or regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
These practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples from uranium-ore concentrates (UOC) and for obtaining a series of representative secondary samples from the original bulk sample for the determination of moisture and other test purposes, and for the preparation of pulverized analytical samples. These practices consist of a number of alternative procedures for (1) primary sampling such as one-stage falling stream, two-stage falling stream, and Auger sampling; (2) secondary sampling such as straight-path (reciprocating) cutter sampling and rotating (Vezin) cutter multi-sampling; (3) sample preparation such as concurrent-drying, natural moisture, and calcination; and (4) sample packaging such as wax sealing and vacuum sealing. These procedures do not include requirements for health, safety, and accountability. The material and sampling equipment requirements are detailed. Schematic diagrams of the primary and secondary samplers are provided.
SCOPE
1.1 These practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples from uranium-ore concentrates (UOC) (see Specification C967).  
1.2 These practices also provide for obtaining a series of representative secondary samples from the original bulk sample for the determination of moisture and other test purposes, and for the preparation of pulverized analytical samples (see Test Methods C1022 and C1843).  
1.3 These practices consist of a number of alternative procedures for sampling and sample preparation which have been shown to be satisfactory through long experience in the nuclear industry. These procedures are described in the following order.    
Stage  
Procedure  
Section  
Primary Sampling  
One-stage falling stream  
5    
Two-stage falling stream  
6    
Auger  
7    
Secondary Sampling  
Straight-path (reciprocating)  
8    
Rotating (Vezin)  
9, 10  
1.3.1 The primary and secondary sampling stages can be organized in the following way:    
1.3.2 It is possible to combine the various elements of these stages in different ways to give satisfactory results depending on the agreed requirements of the contracting parties. For a given stage, however, each procedure must be regarded as a whole. It is highly inadvisable to mix elements belonging to different procedures.  
1.4 These procedures do not include requirements for health, safety, and accountability. The observance of these practices does not relieve the user of the obligation to be aware of and to conform to all applicable international, federal, state, and local regulations pertaining to processing, shipping, or using uranium-ore concentrates. (Guidance is provided in CFR 10, Chapter 1.)  
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.6 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SCOPE
1.1 This specification covers uranium oxides, including processed byproducts or scrap material (powder, pellets, or pieces), that are intended for dissolution into uranyl nitrate solution meeting the requirements of Specification C788 prior to conversion into nuclear grade UO2 powder with a 235U content of less than 5 %. This specification defines the impurity and uranium isotope limits for such urania powders that are to be dissolved prior to processing to nuclear grade UO2 as defined in Specification C753.  
1.2 This specification provides the nuclear industry with a general standard for such uranium oxide powders. It recognizes the diversity of conversion processes and the processes to which such powders are subsequently to be subjected (for instance, by solvent extraction). It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between the buyer and seller.  
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, national, state and local regulations for processing, shipping, or any other way of using urania powders (see 2.2 and 2.3).  
1.4 Units—The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The uranium hexfluoride (UF6), as described in Specifications C787 and C996, has to meet different requirements: one set of requirements being safety, health physics, and criticality and the other set being chemical, physical, and isotopic. To ensure the UF6 is in compliance with all requirements, sampling and analysis shall be performed. Therefore, packaging may have a significant impact on the quality of UF6.  
4.2 After sampling, the bottle will contain residues. There is contamination because of the equipment, other contamination caused by nonvolatile elements, and isotopic contamination as a result of UF6 hydrolysis.  
4.3 Cleaning shall be efficient. Special emphasis should be given to decontaminate the bottles without leaving any trace of cleaning products, make the bottles inert in UF6 medium (passivation bottle), and minimize waste. The cleaning process should be easy, safe, and environmentally friendly.  
4.4 This practice describes different protocols for cleaning bottles by gas and liquid.
SCOPE
1.1 This practice provides a description of the different ways to clean uranium hexafluoride (UF6) bottles.  
1.2 This practice describes two kinds of sample bottles: 1S and 2S bottles.  
1.3 Units—The values stated in SI units are to be regarded as the standard. No other units of measurement are included in this standard.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification covers nuclear-grade, sinterable uranium dioxide (UO2) powder and applies to uranium dioxide powder containing uranium of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors. This specification refers expressly to calcined UO2 powder before the addition of any die lubricant, binder, or pore former, and defines isotopic limits for commercial grade UO2 so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed uranium and. Provisions for preventing criticality accidents or requirements for health and safety are not included in this specification. The powder shall conform to the specified chemical requirements including uranium content, oxygen-to-uranium ratio, impurity content (such as aluminum, carbon, calcium and magnesium, chlorine, fluorine, iron, lead, manganese, molybdenum, nickel, nitrogen, phosphorus, silicon, tantalum, thorium, tin, titanium, tungsten, vanadium, and zinc), moisture content, isotopic content, equivalent boron content, and cleanliness and workmanship. The powder shall also meet the specified physical requirements including particle size, bulk density, and sinterability. Sampling requirements for the test specimen and the test methods for chemical analysis and acceptance testing are detailed.
SCOPE
1.1 This specification covers nuclear-grade, sinterable UO2 powder. It applies to UO2 powder containing uranium (U) of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors.  
1.2 This specification recognizes the presence of reprocessed U in the fuel cycle and consequently defines isotopic limits for commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed U. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.  
1.3 This specification does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material.  
1.4 This specification refers expressly to UO2 powder before the addition of any die lubricant, binder, or pore former. If powder is sold with such additions or prepared as press feed, sampling procedures, allowable impurity contents, or powder physical requirements may need to be modified by agreement between the buyer and the seller.  
1.5 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This practice details the recommended method for calculating the equivalent boron content (EBC) values of nuclear elements and materials that are of potential significance as thermal neutron poisons. EBC factors are determined from the atomic weight of elements and the thermal neutron absorption cross section in barns. These may be used depending upon the actual neutron energy characteristics of the applicable reactor system. The elements aluminum, fluorine, rubidium, barium, lead, silicon, beryllium, neon, tin, bismuth, oxygen, zirconium, carbon, magnesium, cerium, and phosphorus are not required to be included in the EBC calculations as their contribution to the total poison effect is not considerably significant.
SIGNIFICANCE AND USE
4.1 Use of this standard practice yields an equivalent boron content (EBC) that can be used to characterize the neutron-absorbing properties of a nuclear material. The elements included in the calculation are typically chosen so that the EBC represents either the entire material (for example, for a moderator) or the impurities in the material (for example, for a nuclear fuel). This practice is typically used for materials in which thermal neutron absorption is undesirable. The EBC is not intended for use as an input to any neutronic calculation. The EBC factors in Table 1 were selected to represent neutron absorption in water reactors under normal operating conditions. It is the responsibility of the user to evaluate their suitability for other purposes. (A) Neutron Cross Sections , Vol 1, Parts A and B, Academic Press, New York, 1981 and 1984, respectively.(B) Holden, N. E., and Martin, R. L., Pure and Applied Chemistry, Vol 56, p. 653, 1984.(C) When present in small concentrations, this element should be excluded from determinations of the total EBC.(D) In the absence of other data, the neutron capture cross section for a Maxwellian flux is used.(E) Cross section is primarily due to a single isotope, whose isotopic abundance is variable in nature. The value can vary between 733 and 779 barns depending upon the source. See Holden, N. E., Neutron Capture Cross Section Standards for BNL-325, Fourth Ed., BNL-NCS-51388, January 1981.(F) Cross section is primarily due to a single isotope, whose isotopic abundance is variable in nature. The value can vary between 69 and 72 barns depending upon the source. See Holden, N. E., Neutron Capture Cross Section Standards for BNL-325, Fourth Ed., BNL-NCS-51388, January 1981.
SCOPE
1.1 This standard details a recommended practice for the calculation of the Equivalent Boron Content (EBC) for nuclear materials. The EBC is used to provide a measure of the macroscopic neutron absorption cross section of a nuclear material. EBC factors for the natural elements are determined from their atomic masses and thermal neutron absorption cross sections. This practice is illustrated by using EBC factors that are based on thermal neutron (2200 m/s) absorption cross sections. Other EBC factors may be used depending upon the actual neutron energy spectrum.  
1.2 The EBC is a characteristic of a homogeneous material. Characterization of inhomogeneous materials and calculation of neutron multiplication factors require techniques that are beyond the scope of this practice.  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification covers nuclear grade uranium metal that has either been processed through an enrichment plant, or has been produced by the blending of highly enriched uranium with other uranium, to obtain uranium of any 235U concentration below 20 % (and greater than 15 %) and that is intended for research reactor fuel fabrication. The uranium content of commercial grade enriched uranium metal shall be greater than or equal to 99.85 weight percent. The isotopic requirements for enriched uranium metal are presented in details. The chemical and isotopic composition shall be tested to meet the requirements prescribed.
SCOPE
1.1 This specification covers nuclear grade uranium metal that has either been processed through an enrichment plant, or has been produced by the blending of highly enriched uranium with other uranium, to obtain uranium of any  235U mass fraction below 20 % and that is intended for research reactor and generation IV nuclear reactor fuel fabrication. The scope of this specification includes specifications for enriched uranium metal derived from commercial natural uranium, reprocessed uranium, or highly enriched uranium. Commercial natural uranium, reprocessed uranium and highly enriched uranium are defined in Section 3. The objectives of this specification are to define the impurity and uranium isotope limits for commercial grade enriched uranium metal.  
1.2 This specification is intended to provide the nuclear industry with a standard for enriched uranium metal which is to be used in the production of research reactor and generation IV nuclear reactor fuel. In addition to this specification, the parties concerned may agree to other appropriate conditions.  
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this standard does not relieve the user of the obligation to conform to all applicable international, federal, state, and local regulations for processing, shipping, or any other way of using uranium metal (see, for example, C996 regarding references).  
1.4 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification covers sinterable nuclear-grade plutonium dioxide powders obtained by the oxalate precipitation route, calcination, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium, or recycled plutonium mixed with uranium. The material shall conform to required chemical compositions of plutonium, uranium, americium, impurities (boron, cadmium, carbon, chlorine, chromium, fluorine, iron, gadolinium, nickel, nitride nitrogen, and thorium), equivalent boron, and gamma activity. Materials shall also adhere to physical property requirements as to cleanliness and workmanship, particle size, and surface area.
SCOPE
1.1 This specification covers nuclear grade PuO2 powder. It applies to PuO2 of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium or by in-reactor neutron irradiation of recycled plutonium mixed with uranium.  
1.2 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. For examples in the U.S. Government, relevant documents are Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-70162, and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission Report, DP-5322.  
1.3 The PuO2 shall be produced by a qualified process and in accordance with a quality assurance program approved by the user.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5% 235U intended for subsequent manufacture into either UF6 or direct conversion to uranium oxide. This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or crystals. The purpose of this specification is: to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate).
SCOPE
1.1 This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5 %  235U intended for subsequent manufacture into either UF6  (for feed to an enrichment plant) or direct conversion to uranium oxide (for use in reactors).  
1.2 This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or crystals. It recognizes the diversity of manufacturing methods and the processes to which it is subsequently to be subjected. It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between purchaser and manufacturer. Different limits are appropriate depending on whether or not the uranyl nitrate is to be converted to UF6  for subsequent processing.  
1.3 The purpose of this specification is: (a) to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and (b) to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate). For such uranyl nitrates, special provisions may need to be made to ensure that no extra hazard arises to the employees, the process equipment, or the environment.  
1.4 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this standard does not relieve the user of the obligation to conform to all international, federal, state and local regulations for processing, shipping, or any other way of using the uranyl nitrate. An example of a U.S. Government Document is the Code of Federal Regulations, Title 10, Part 50 (latest edition).  
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
5.1 Facility operators and safeguards inspectors routinely collect UF6 samples from processing lines, isotopic enrichment cascades or storage cylinders to determine uranium isotopic composition. The isotope ratio n(235U)/n(238U) is particularly important since it is used to calculate the amount of fissile 235U in the sample.  
5.2 Conventional sampling practices (such as Practices C1052 and C1703) collect samples of UF6, usually in quantities greater than one gram. Due to the chemical hazards of UF6 (and in some cases the high collection mass), an increasing number of air transport operators are unwilling to transport such samples. In contrast, SUDA samples are expected to be transported as excepted quantities (for example, under UN 2910 (3)), as the conversion to a less hazardous, more stable chemical species avoids the chemical hazards of UF6 similar to Practice C1880. Additionally, the decreased shipping requirement and small collection mass of SUDA samplers (less than Practice C1880) allow for multiple SUDA samples to be transported in the same shipment.  
5.3 For safeguards applications, isotopic measurements that fall within the 2010 International Target Value (ITV) ranges (5) have been demonstrated (1).  
5.4 This practice provides the following qualities:  
5.4.1 Fitness for purpose in verifying nuclear material declarations.  
5.4.2 A safe, simple and fast procedure for the sample collector that minimizes sample handling and potential for cross-contamination.  
5.4.3 Flexibility for use in a wide variety of facilities.  
5.4.4 Robustness to adapt to minor changes in facility operating parameters.  
5.4.5 Confidentiality for the operating facility from which the sample is collected.  
5.4.6 Safety in sample handling and transport since the sample is a less hazardous, more stable form (specifically, UO2F2 is more stable and less volatile than UF6 gas).  
5.4.7 Ease of sample preparation in the laboratory with reduced processing hazards during recove...
SCOPE
1.1 This practice is applicable to sampling gaseous uranium hexafluoride (UF6) from processing facilities, isotope enrichment cascades or storage cylinders, using the sorbent properties of zeolite in a single-use destructive assay (SUDA) sampler.  
1.2 This practice is based on the SUDA method developed at Pacific Northwest National Laboratory (1)2 for collection of samples of UF6 for determination of uranium isotopic content for nuclear material safeguards and other applications.  
1.3 The UF6 collected is converted to uranyl fluoride (UO2F2), allowing samples to be handled and categorized for transport under less stringent conditions than are required for UF6.  
1.4 This practice can be used to collect samples for safeguards measurements. Safeguards samples collected with this practice have been shown to provide suitable isotopic measurements (1).  
1.5 This practice has not been demonstrated for suitability for compliance with Specifications C787 and C996. Practices C1052 or C1703 can be used to collect samples for compliance with these specifications.  
1.6 The scope of this practice does not include provisions for preventing criticality.  
1.7 Units—The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
1.8 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.9 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Bar...

ABSTRACT
This specification covers finished pellets composed of sintered gadolinium oxide-uranium dioxide of any concentration for use in light-water reactors. Materials shall adhere to specified chemical (impurity content, stoichiometry, moisture content, and gadolinium oxide concentration), nuclear (isotopic content), and physical (dimensions, density, homogeneity, integrity, axial and circumferential surface cracks, cylindrical surface chips, pellets ends, cleanliness and workmanship, identification, and irradiation stability) requirements.
SCOPE
1.1 This specification is for finished sintered (U,Gd)O2 pellets. It applies to (U,Gd)O2 pellets containing uranium (U) of any  235U concentration and any concentration of gadolinium oxide (Gd2O3) for use in nuclear reactors.  
1.2 This specification recognizes the presence of reprocessed U in the fuel cycle and consequently defines isotopic limits for (U,Gd)O2 pellets made from commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unirradiated U. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.  
1.3 This specification does not include (a) provisions for preventing criticality accidents, (b) requirements for health and safety, (c) avoidance of hazards, or (d) shipping precautions and controls. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. Examples of U.S. Governmental documents are Code of Federal Regulations (Latest Edition), Title 10, Part 50, Title 10, Part 70, Title 10, Part 71, and Title 49, Part 173.  
1.4 Units—The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 The following precautionary caveat pertains only to the technical requirements portion, Section 4, of this specification: This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
5.1 Uranium hexafluoride is normally produced and handled in large (typically 1- to 20-ton) quantities and must, therefore, be characterized by reference to representative samples. The quantities involved, physical properties, chemical reactivity, and hazardous nature of UF6 are such that for representative sampling, specially designed equipment must be used and operated in accordance with the most carefully controlled and stringent procedures. This practice indicates appropriate principles, equipment, and procedures currently in use for bulk sampling of liquid UF6. It is used by UF6 converters, enrichers, and fuel fabricators to review the effectiveness of existing procedures or as a guide to the design of equipment and procedures for future use.  
5.2 It is emphasized that this practice is not meant to address conventional or nuclear criticality safety issues.
SCOPE
1.1 This practice covers methods for withdrawing representative samples of liquid uranium hexafluoride (UF6) from bulk quantities of the material. Such samples are then prepared for further analytical testing in accordance with Practices C1689 and C1346. Multiple different methods are used for determining compliance with the applicable commercial specification, for example Specifications C787 and C996. Methods used for compliance to each of these standards can be found in the Referenced Documents section of each respective specification.  
1.2 It is assumed that the bulk liquid UF6 being sampled comprises a single quality and quantity of material. This practice does not address any special additional arrangements that might be required for taking proportional or composite samples. When the sampled bulk material is being added to UF6 residues already in a container (“heels recycle”) additional arrangements are required to avoid cross contamination of the bulk UF6, these are addressed in Specifications C787 and C996.  
1.3 The number of samples to be taken, their nominal sample weight, and their disposition shall be agreed upon between the parties.  
1.4 The scope of this practice does not include provisions for preventing criticality incidents.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification covers nuclear grade uranium hexafluoride (UF6) that has been processed through an enrichment plant or produced by blending highly enriched uranium with other uranium to produce a concentration suitable for nuclear fuel fabrication. This specification defines the impurity and uranium isotope limits for the enriched commercial grade UF6 and for enriched reprocessed UF6. All materials should conform to the specified chemical, physical, and isotopic requirements.
SCOPE
1.1 This specification covers nuclear grade uranium hexafluoride (UF6) that either has been processed through an enrichment plant or has been produced by the blending of Highly Enriched Uranium with other uranium to obtain uranium of any  235U concentration below 5 % and that is intended for fuel fabrication. The objectives of this specification are twofold: (1) to define the impurity and uranium isotope limits for Enriched Commercial Grade UF6 so that, with respect to fuel design and manufacture, it is essentially equivalent to enriched uranium made from natural UF6, and (2) to define limits for Enriched Reprocessed UF6  to be expected if Reprocessed UF6 is to be enriched without dilution with Commercial Natural UF6. For such UF6, special provisions, not defined herein, may be needed to ensure fuel performance and to protect the work force, process equipment, and the environment.  
1.2 This specification is intended to provide the nuclear industry with a standard for enriched UF6 that is to be used in the production of sinterable UO2 powder for fuel fabrication. In addition to this specification, the parties concerned may agree to other appropriate conditions.  
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all applicable international, federal, state, and local regulations for processing, shipping, or in any other way using UF6  (see, for example, TID-7016, DP-532, and DOE O474.1).  
1.4 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification covers uranium hexafluoride intended for feeding to an enrichment plant. Plants preparing uranium hexafluoride will have to control the purity of process chemicals and also employ low corrosion equipment to be successful in meeting the specifications for most impurities. Chemical and isotopic analysis of the material shall conform to the requirements prescribed.
SCOPE
1.1 This specification covers uranium hexafluoride (UF6) intended for feeding to an enrichment plant. Included are specifications for UF6 derived from unirradiated natural uranium and UF6 derived from irradiated uranium that has been reprocessed and converted to UF6 for enrichment and subsequent reuse. The objectives of this specification are twofold: (1) to define the impurity and uranium isotope limits for Commercial Natural UF6 feedstock, and (2) to define additional limits for Reprocessed UF6 (or any mixture of Reprocessed UF6 and Commercial Natural UF6). For such UF6, special provisions may be needed to ensure that no extra hazard arises to the work force, process equipment, or the environment.  
1.2 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, federal, state, and local regulations for processing, shipping, or in any other way using UF6 (for example, see TID-7016, DP-532, ORNL-NUREG-CSD-6, and DOE O 474.1).  
1.3 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification covers uranium ore concentrate. Chemical composition shall have a minimum content requirement for uranium and a limited content for uranium isotope, insoluble uranium, extractable organic, and impurities. Uranium ore shall also conform to chemical analyses, particle size, flow ability, and foreign matter contents according to the specification. Standard packaging requirements for uranium ore shall also be met according to the specification.
SCOPE
1.1 This specification covers uranium ore concentrate containing a minimum of 65 mass % uranium.  
1.2 This specification does not include requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, national, state, and local regulations pertaining to possessing, shipping, or using source nuclear material (see 2.2).  
1.3 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
5.1 The standard method for taking representative UF6 sample from a cylinder is collecting from UF6 liquid phase. Homogeneity of material is obtained by the basic indicator, that is, content of uranium isotope. Representativeness of a sample by other indicators such as content of highly volatile admixtures (boron fluoride, silicon fluoride, organic impurities), admixtures generating non-volatile fluorides may not be satisfactory owing to differences between physical properties of admixture and UF6. Nevertheless, such sampling is widely applied during the product quality control due to the fact that liquid phase process is applied when filling transport containers both for feedstock UF6 and enriched one. Refer to Practice C1052 for UF6 liquid phase sampling practice.  
5.2 Uranium hexafluoride is normally produced and handled in large (typically 1 to 14-ton) quantities and must, therefore, be characterized by reference to representative samples (see ISO 7195:2005). The samples are used to determine compliance with the applicable commercial Specification C996. The quantities involved, physical properties, chemical reactivity, and hazardous nature of UF6 are such that for representative sampling, specially designed equipment must be used and operated in accordance with the most carefully controlled and stringent procedures. This practice can be used by UF6 enrichers to review the effectiveness of existing procedures or as a guide to the design of equipment and procedures for future use.  
5.3 It is emphasized that this practice is not meant to address conventional or nuclear criticality safety issues.
SCOPE
1.1 This practice covers the methods for withdrawing samples of enriched uranium hexafluoride (UF6) during and after a transfer occurring in the gas phase in order to determine compliance with Specification C996. It is applicable to the filling of a transport UF6 container (30B cylinder or 1 m3 vertical container) at a centrifuge enrichment facility that has been fed with UF6 that complies with Specification C787.  
1.2 Since UF6 sampling is taken during the filling process, this practice does not address any special additional arrangements that may be agreed upon between the buyer and the seller when the sampled bulk material is being added to residues already present in a container (“heels recycle”). Such arrangements will be based on QA procedures such as traceability of cylinder origin (to prevent, for example, contamination with irradiated material).  
1.3 This practice is only applicable when the transfer occurs in the gas phase. When the transfer is performed in the liquid phase, Practice C1052 should apply.  
1.4 The scope of this practice does not include provisions for preventing criticality incidents.  
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
5.1 Facility operators and safeguards inspectors routinely take UF6 samples from processing lines, isotopic enrichment cascades or storage cylinders to determine its U isotopic composition, most important the n(235U)/n(238U) isotope ratio, needed to calculate the amount of the fissile 235U in the sample. The current version of the “International Target Values for Measurement Uncertainties in Safeguarding Nuclear Materials” (3) contains recommended guidelines for these measurements.  
5.2 The conventional sampling practice collects UF6 samples in the range of 1-10 g and requires the use of liquid nitrogen to condense them in sample vessels, metallic bottles or P-10 tubes. These samples must then be transported to external analytical laboratories for verification of the declared data, especially the isotope ratios. Transport includes, among other things, public roads and intercontinental air shipment. Due to the hazards of UF6, air transport is becoming increasingly difficult, with many transport operators and regulators refusing to carry the material.  
5.3 This sampling practice was developed to meet the following requirements:  
5.3.1 Fit for Purpose: to enable the verification of the declarations of amounts of nuclear materials.  
5.3.2 Simplicity: to ensure a simple and fast execution.  
5.3.3 Flexibility: to be applied in a wide range of facilities.  
5.3.4 Robustness: to ensure sufficient material is sampled even when operational parameters slightly change.  
5.3.5 Reliability: to provide measurement results in agreement with those obtained using the conventional sampling practice.  
5.3.6 Confidentiality: to respect the facility’s operational procedure and confidentiality of data.  
5.3.7 Safety: to reduce the risks associated with the sampling, handling and transport of radioactive and hazardous materials.  
5.4 This sampling practice offers significant advantages over the conventional sampling practice because it allows handling non-reactive, non-v...
SCOPE
1.1 This practice is applicable to sampling gaseous uranium hexafluoride (UF6) from processing facilities, isotope enrichment cascades or storage cylinders, using the sorbent properties of aluminum oxide (Al2O3).  
1.2 It is based on the ‘ABACC-Cristallini Method’ (1, 2)2 and is intended to be used for the determination of uranium (U) isotopic composition required for nuclear material safeguards as well as other applications.  
1.3 The application of this practice assures the resulting sample vessel contains no UF6 and hydrogen fluoride (HF); therefore, it may be handled and categorized for transport under less stringent constraints.  
1.4 The scope of this practice does not include provisions for preventing criticality.  
1.5 Units—The values stated in SI units are to be regarded as the standard. When non-SI units are provided, they are for information only.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
5.1 Uranium hexafluoride is normally produced and handled in large (typically 1 to 14-ton) quantities and must, therefore, be characterized by reference to representative samples (see ISO 7195). The samples are used to determine compliance with the applicable commercial specification C787. The quantities involved, physical properties, chemical reactivity, and hazardous nature of UF6 are such that for representative sampling, specially designed equipment must be used and operated in accordance with the most carefully controlled and stringent procedures. This practice can be used by UF6 converters to review the effectiveness of existing procedures or as a guide to the design of equipment and procedures for future use.  
5.2 The intention of this practice is to avoid liquid UF6 sampling once the cylinder has been filled. For safety reasons, manipulation of large quantities of liquid UF6 should be avoided when possible.  
5.3 It is emphasized that this practice is not meant to address conventional or nuclear criticality safety issues.
SCOPE
1.1 This practice covers methods for withdrawing representative sample(s) of uranium hexafluoride (UF6) during a transfer occurring in the gas phase. Such transfer in the gas phase can take place during the filling of a cylinder during a continuous production process, for example the distillation column in a conversion facility. Such sample(s) may be used for determining compliance with the applicable commercial specification, for example Specification C787.  
1.2 Since UF6 sampling is taken during the filling process, this practice does not address any special additional arrangements that may be agreed upon between the buyer and the seller when the sampled bulk material is being added to residues already present in a container (“heels recycle”). Such arrangements will be based on QA procedures such as traceability of cylinder origin (to prevent for example contamination with irradiated material).  
1.3 If the receiving cylinder is purged after filling and sampling, special verifications must be performed by the user to verify the representativity of the sample(s). It is then expected that the results found on volatile impurities with gas phase sampling may be conservative.  
1.4 This practice is only applicable when the transfer occurs in the gas phase. When the transfer is performed in the liquid phase, Practice C1052 should apply. This practice does not apply to gas sampling after the cylinder has been filled since the sample taken will not be representative of the cylinder.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
These practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples from uranium-ore concentrates (UOC) and for obtaining a series of representative secondary samples from the original bulk sample for the determination of moisture and other test purposes, and for the preparation of pulverized analytical samples. These practices consist of a number of alternative procedures for (1) primary sampling such as one-stage falling stream, two-stage falling stream, and Auger sampling; (2) secondary sampling such as straight-path (reciprocating) cutter sampling and rotating (Vezin) cutter multi-sampling; (3) sample preparation such as concurrent-drying, natural moisture, and calcination; and (4) sample packaging such as wax sealing and vacuum sealing. These procedures do not include requirements for health, safety, and accountability. The material and sampling equipment requirements are detailed. Schematic diagrams of the primary and secondary samplers are provided.
SCOPE
1.1 These practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples from uranium-ore concentrates (UOC) (see Specification C967).  
1.2 These practices also provide for obtaining a series of representative secondary samples from the original bulk sample for the determination of moisture and other test purposes, and for the preparation of pulverized analytical samples (see Test Methods C1022 and C1843).  
1.3 These practices consist of a number of alternative procedures for sampling and sample preparation which have been shown to be satisfactory through long experience in the nuclear industry. These procedures are described in the following order.    
Stage  
Procedure  
Section  
Primary Sampling  
One-stage falling stream  
5    
Two-stage falling stream  
6    
Auger  
7    
Secondary Sampling  
Straight-path (reciprocating)  
8    
Rotating (Vezin)  
9, 10  
1.3.1 The primary and secondary sampling stages can be organized in the following way:    
1.3.2 It is possible to combine the various elements of these stages in different ways to give satisfactory results depending on the agreed requirements of the contracting parties. For a given stage, however, each procedure must be regarded as a whole. It is highly inadvisable to mix elements belonging to different procedures.  
1.4 These procedures do not include requirements for health, safety, and accountability. The observance of these practices does not relieve the user of the obligation to be aware of and to conform to all applicable international, federal, state, and local regulations pertaining to processing, shipping, or using uranium-ore concentrates. (Guidance is provided in CFR 10, Chapter 1.)  
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.6 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification covers sintered uranium dioxide pellets containing 235U for use in nuclear reactors. Chemical requirements include uranium content, impurity content, stoichiometry, and moisture content. Maximum concentration limits are specified for impurity elements such as: aluminum, carbon, calcium+magnesium, chlorine, chromium, cobalt, fluorine, hydrogen, iron, nickel, nitrogen, silicon, and thorium. Chemical analyses shall be performed. Nuclear requirements include isotopic content and equivalent boron content. The following are physical characteristics of the material: dimensions, pellet density, grain size and pore morphology, pellet integrity –
SCOPE
1.1 This specification is for finished sintered UO2 pellets. It applies to UO2 pellets containing uranium (U) of any  235U concentration for use in nuclear reactors.  
1.2 This specification recognizes the presence of reprocessed U in the fuel cycle and consequently defines isotopic limits for UO2 pellets made from commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unirradiated U. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.  
1.3 This specification does not include (a) provisions for preventing criticality accidents, (b) requirements for health and safety, (c) avoidance of hazards, or (d) shipping precautions and controls. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. Examples of U.S. Government documents are Code of Federal Regulations (Latest Edition), Title 10, Part 50, Title 10, Part 70, Title 10, Part 71, and Title 49, Part 173.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 The following precautionary caveat pertains only to the technical requirements portion, Section 4, of this specification:  This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability or regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

ABSTRACT
This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
SCOPE
1.1 This specification covers finished sintered and ground (U, Pu)O2 pellets for use in light water reactors. It applies to (U, Pu)O2 pellets containing plutonium additions up to 15 weight % (wt%; that is, 0.15 g Pu / g (U + Pu + Am)).  
1.2 Pellets produced under this specification are available in four grades.  
1.2.1 Grade R—240Pu content of (Pu + Am) (that is, g  240Pu / g (Pu + Am)) is at least 19 %.  
1.2.2 Grade F—240Pu content of (Pu + Am) is at least 7 % and less than 19 %.  
1.2.3 Grade N1—240Pu content of (Pu + Am) is less than 7 %.  
1.2.4 Grade N2—240Pu /239Pu does not exceed 0.10.  
1.3 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50—Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71—Packaging and Transportation of Radioactive Material; and Code of Federal Regulations Title 49, Part 173—General Requirements for Shipments and Packaging.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 The following safety hazards caveat pertains only to the technical requirements portion, Section 4, of this specification: This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This specification covers nuclear-grade, sinterable uranium dioxide (UO2) powder and applies to uranium dioxide powder containing uranium of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors. This specification refers expressly to calcined UO2 powder before the addition of any die lubricant, binder, or pore former, and defines isotopic limits for commercial grade UO2 so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed uranium and. Provisions for preventing criticality accidents or requirements for health and safety are not included in this specification. The powder shall conform to the specified chemical requirements including uranium content, oxygen-to-uranium ratio, impurity content (such as aluminum, carbon, calcium and magnesium, chlorine, fluorine, iron, lead, manganese, molybdenum, nickel, nitrogen, phosphorus, silicon, tantalum, thorium, tin, titanium, tungsten, vanadium, and zinc), moisture content, isotopic content, equivalent boron content, and cleanliness and workmanship. The powder shall also meet the specified physical requirements including particle size, bulk density, and sinterability. Sampling requirements for the test specimen and the test methods for chemical analysis and acceptance testing are detailed.
SCOPE
1.1 This specification covers nuclear-grade, sinterable UO2 powder. It applies to UO2 powder containing uranium (U) of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors.  
1.2 This specification recognizes the presence of reprocessed U in the fuel cycle and consequently defines isotopic limits for commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed U. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.  
1.3 This specification does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material.  
1.4 This specification refers expressly to UO2 powder before the addition of any die lubricant, binder, or pore former. If powder is sold with such additions or prepared as press feed, sampling procedures, allowable impurity contents, or powder physical requirements may need to be modified by agreement between the buyer and the seller.  
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory requirements prior to use.

ABSTRACT
This specification covers sinterable nuclear-grade plutonium dioxide powders obtained by the oxalate precipitation route, calcination, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium, or recycled plutonium mixed with uranium. The material shall conform to required chemical compositions of plutonium, uranium, americium, impurities (boron, cadmium, carbon, chlorine, chromium, fluorine, iron, gadolinium, nickel, nitride nitrogen, and thorium), equivalent boron, and gamma activity. Materials shall also adhere to physical property requirements as to cleanliness and workmanship, particle size, and surface area.
SCOPE
1.1 This specification covers nuclear grade PuO2 powder. It applies to PuO2 of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium or by in-reactor neutron irradiation of recycled plutonium mixed with uranium.  
1.2 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. For examples in the U.S. Government, relevant documents are Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-70162, and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission Report, DP-5322.  
1.3 The PuO2 shall be produced by a qualified process and in accordance with a quality assurance program approved by the user.  
1.4 The values stated in SI units are to be regarded as the standard.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This specification covers sinterable nuclear-grade plutonium dioxide powders obtained by the oxalate precipitation route, calcination, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium, or recycled plutonium mixed with uranium. The material shall conform to required chemical compositions of plutonium, uranium, americium, impurities (boron, cadmium, carbon, chlorine, chromium, fluorine, iron, gadolinium, nickel, nitride nitrogen, and thorium), equivalent boron, and gamma activity. Materials shall also adhere to physical property requirements as to cleanliness and workmanship, particle size, and surface area.
SCOPE
1.1 This specification covers nuclear grade PuO2 powder. It applies to PuO2 of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium or by in-reactor neutron irradiation of recycled plutonium mixed with uranium.  
1.2 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. For examples in the U.S. Government, relevant documents are Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-70162, and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission Report, DP-5322.  
1.3 The PuO2 shall be produced by a qualified process and in accordance with a quality assurance program approved by the user.  
1.4 The values stated in SI units are to be regarded as the standard.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 The uranium hexfluoride (UF6), as described in Specifications C787 and C996, has to meet different requirements: one set of requirements being safety, health physics, and criticality and the other set being chemical, physical, and isotopic. To ensure the UF6 is in compliance with all requirements, sampling and analysis shall be performed. Therefore, packaging may have a significant impact on the quality of UF6.  
4.2 After sampling, the bottle will contain residues. There is contamination because of the equipment, other contamination caused by nonvolatile elements, and isotopic contamination as a result of UF6 hydrolysis.  
4.3 Cleaning shall be efficient. Special emphasis should be given to decontaminate the bottles without leaving any trace of cleaning products, make the bottles inert in UF6 medium (passivation bottle), and minimize waste. The cleaning process should be easy, safe, and environmentally friendly.  
4.4 This practice describes different protocols for cleaning bottles by gas and liquid.
SCOPE
1.1 This practice provides a description of the different ways to clean uranium hexafluoride (UF6) bottles.  
1.2 This practice describes two kinds of sample bottles: 1S and 2S bottles.  
1.3 Units—The values stated in SI units are to be regarded as the standard. No other units of measurement are included in this standard.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This specification covers nuclear-grade, sinterable uranium dioxide (UO2) powder and applies to uranium dioxide powder containing uranium of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors. This specification refers expressly to calcined UO2 powder before the addition of any die lubricant, binder, or pore former, and defines isotopic limits for commercial grade UO2 so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed uranium and. Provisions for preventing criticality accidents or requirements for health and safety are not included in this specification. The powder shall conform to the specified chemical requirements including uranium content, oxygen-to-uranium ratio, impurity content (such as aluminum, carbon, calcium and magnesium, chlorine, fluorine, iron, lead, manganese, molybdenum, nickel, nitrogen, phosphorus, silicon, tantalum, thorium, tin, titanium, tungsten, vanadium, and zinc), moisture content, isotopic content, equivalent boron content, and cleanliness and workmanship. The powder shall also meet the specified physical requirements including particle size, bulk density, and sinterability. Sampling requirements for the test specimen and the test methods for chemical analysis and acceptance testing are detailed.
SCOPE
1.1 This specification covers nuclear-grade, sinterable UO2 powder. It applies to UO2 powder containing uranium (U) of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors.  
1.2 This specification recognizes the presence of reprocessed U in the fuel cycle and consequently defines isotopic limits for commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed U. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.  
1.3 This specification does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material.  
1.4 This specification refers expressly to UO2 powder before the addition of any die lubricant, binder, or pore former. If powder is sold with such additions or prepared as press feed, sampling procedures, allowable impurity contents, or powder physical requirements may need to be modified by agreement between the buyer and the seller.  
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory requirements prior to use.

SCOPE
1.1 This specification covers uranium oxides, including processed byproducts or scrap material (powder, pellets, or pieces), that are intended for dissolution into uranyl nitrate solution meeting the requirements of Specification C788 prior to conversion into nuclear grade UO2 powder with a  235U content of less than 5 %. This specification defines the impurity and uranium isotope limits for such urania powders that are to be dissolved prior to processing to nuclear grade UO2 as defined in Specification C753.  
1.2 This specification provides the nuclear industry with a general standard for such uranium oxide powders. It recognizes the diversity of conversion processes and the processes to which such powders are subsequently to be subjected (for instance, by solvent extraction). It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between the buyer and seller.  
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, national, state and local regulations for processing, shipping, or any other way of using urania powders (see 2.2 and 2.3).

ABSTRACT
This specification covers nuclear grade uranium hexafluoride (UF6) that has been processed through an enrichment plant or produced by blending highly enriched uranium with other uranium to produce a concentration suitable for nuclear fuel fabrication. This specification defines the impurity and uranium isotope limits for the enriched commercial grade UF6 and for enriched reprocessed UF6. All materials should conform to the specified chemical, physical, and isotopic requirements.
SCOPE
1.1 This specification covers nuclear grade uranium hexafluoride (UF6) that either has been processed through an enrichment plant, or has been produced by the blending of Highly Enriched Uranium with other uranium to obtain uranium of any  235U concentration below 5 % and that is intended for fuel fabrication. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Enriched Commercial Grade UF6 so that, with respect to fuel design and manufacture, it is essentially equivalent to enriched uranium made from natural UF6; and (2) To define limits for Enriched Reprocessed UF6  to be expected if Reprocessed UF6 is to be enriched without dilution with Commercial Natural UF6. For such UF6, special provisions, not defined herein, may be needed to ensure fuel performance and to protect the work force, process equipment, and the environment.  
1.2 This specification is intended to provide the nuclear industry with a standard for enriched UF6 that is to be used in the production of sinterable UO2 powder for fuel fabrication. In addition to this specification, the parties concerned may agree to other appropriate conditions.  
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all applicable international, federal, state, and local regulations for processing, shipping, or in any other way using UF6  (see, for example, TID-7016, DP-532, and DOE O474.1).  
1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

ABSTRACT
This specification covers uranium hexafluoride intended for feeding to an enrichment plant. Plants preparing uranium hexafluoride will have to control the purity of process chemicals and also employ low corrosion equipment to be successful in meeting the specifications for most impurities. Chemical and isotopic analysis of the material shall conform to the requirements prescribed.
SCOPE
1.1 This specification covers uranium hexafluoride (UF6) intended for feeding to an enrichment plant. Included are specifications for UF6 derived from unirradiated natural uranium and UF6 derived from irradiated uranium that has been reprocessed and converted to UF6 for enrichment and subsequent reuse. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Commercial Natural UF6 feedstock; and (2) To define additional limits for Reprocessed UF6 (or any mixture of Reprocessed UF6 and Commercial Natural UF6). For such UF6, special provisions may be needed to ensure that no extra hazard arises to the work force, process equipment, or the environment.  
1.2 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, federal, state, and local regulations for processing, shipping, or in any other way using UF6 (see, for example, TID-7016, DP-532, ORNL-NUREG-CSD-6, and DOE O 474.1).  
1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

ABSTRACT
This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5% 235U intended for subsequent manufacture into either UF6 or direct conversion to uranium oxide. This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or crystals. The purpose of this specification is: to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate).
SCOPE
1.1 This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5 %  235U intended for subsequent manufacture into either UF6  (for feed to an enrichment plant) or direct conversion to uranium oxide (for use in reactors).  
1.2 This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or crystals. It recognizes the diversity of manufacturing methods and the processes to which it is subsequently to be subjected. It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between purchaser and manufacturer. Different limits are appropriate depending on whether or not the uranyl nitrate is to be converted to UF6  for subsequent processing.  
1.3 The purpose of this specification is: (a) to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and (b) to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate). For such uranyl nitrates, special provisions may need to be made to ensure that no extra hazard arises to the employees, the process equipment, or the environment.  
1.4 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this standard does not relieve the user of the obligation to conform to all international, federal, state and local regulations for processing, shipping, or any other way of using the uranyl nitrate. An example of a U.S. Government Document is the Code of Federal Regulations, Title 10, Part 50 (latest edition).  
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This practice details the recommended method for calculating the equivalent boron content (EBC) values of nuclear elements and materials that are of potential significance as thermal neutron poisons. EBC factors are determined from the atomic weight of elements and the thermal neutron absorption cross section in barns. These may be used depending upon the actual neutron energy characteristics of the applicable reactor system. The elements aluminum, fluorine, rubidium, barium, lead, silicon, beryllium, neon, tin, bismuth, oxygen, zirconium, carbon, magnesium, cerium, and phosphorus are not required to be included in the EBC calculations as their contribution to the total poison effect is not considerably significant.
SIGNIFICANCE AND USE
4.1 Use of this standard practice yields an equivalent boron content (EBC) that can be used to characterize the neutron-absorbing properties of a nuclear material. The elements included in the calculation are typically chosen so that the EBC represents either the entire material (for example, for a moderator) or the impurities in the material (for example, for a nuclear fuel). This practice is typically used for materials in which thermal neutron absorption is undesirable. The EBC is not intended for use as an input to any neutronic calculation. The EBC factors in Table 1 were selected to represent neutron absorption in water reactors under normal operating conditions. It is the responsibility of the user to evaluate their suitability for other purposes. (A) Neutron Cross Sections , Vol 1, Parts A and B, Academic Press, New York, 1981 and 1984, respectively.(B) Holden, N. E., and Martin, R. L., Pure and Applied Chemistry, Vol 56, p. 653, 1984.(C) When present in small concentrations, this element should be excluded from determinations of the total EBC.(D) In the absence of other data, the neutron capture cross section for a Maxwellian flux is used.(E) Cross section is primarily due to a single isotope, whose isotopic abundance is variable in nature. The value can vary between 733 and 779 barns depending upon the source. See Holden, N. E., Neutron Capture Cross Section Standards for BNL-325, Fourth Ed., BNL-NCS-51388, January 1981.(F) Cross section is primarily due to a single isotope, whose isotopic abundance is variable in nature. The value can vary between 69 and 72 barns depending upon the source. See Holden, N. E., Neutron Capture Cross Section Standards for BNL-325, Fourth Ed., BNL-NCS-51388, January 1981.
SCOPE
1.1 This standard details a recommended practice for the calculation of the Equivalent Boron Content (EBC) for nuclear materials. The EBC is used to provide a measure of the macroscopic neutron absorption cross section of a nuclear material. EBC factors for the natural elements are determined from their atomic masses and thermal neutron absorption cross sections. This practice is illustrated by using EBC factors that are based on thermal neutron (2200 m/s) absorption cross sections. Other EBC factors may be used depending upon the actual neutron energy spectrum.  
1.2 The EBC is a characteristic of a homogeneous material. Characterization of inhomogeneous materials and calculation of neutron multiplication factors require techniques that are beyond the scope of this practice.  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

SIGNIFICANCE AND USE
5.1 Uranium hexafluoride is normally produced and handled in large (typically 1- to 20-ton) quantities and must, therefore, be characterized by reference to representative samples. The quantities involved, physical properties, chemical reactivity, and hazardous nature of UF6 are such that for representative sampling, specially designed equipment must be used and operated in accordance with the most carefully controlled and stringent procedures. This practice indicates appropriate principles, equipment, and procedures currently in use for bulk sampling of liquid UF6. It is used by UF6 converters, enrichers, and fuel fabricators to review the effectiveness of existing procedures or as a guide to the design of equipment and procedures for future use.  
5.2 It is emphasized that this practice is not meant to address conventional or nuclear criticality safety issues.
SCOPE
1.1 This practice covers methods for withdrawing representative samples of liquid uranium hexafluoride (UF6) from bulk quantities of the material. Such samples are used for determining compliance with the applicable commercial specification, for example Specification C787 and Specification C996.  
1.2 It is assumed that the bulk liquid UF6 being sampled comprises a single quality and quantity of material. This practice does not address any special additional arrangements that might be required for taking proportional or composite samples. When the sampled bulk material is being added to UF6 residues already in a container (“heels recycle”) additional arrangements are required to avoid cross contamination of the bulk UF6, these are addressed in the appropriate section (8.2) of Specifications C787 and C996.  
1.3 The number of samples to be taken, their nominal sample weight, and their disposition shall be agreed upon between the parties.  
1.4 The scope of this practice does not include provisions for preventing criticality incidents.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This specification covers finished pellets composed of sintered gadolinium oxide-uranium dioxide of any concentration for use in light-water reactors. Materials shall adhere to specified chemical (impurity content, stoichiometry, moisture content, and gadolinium oxide concentration), nuclear (isotopic content), and physical (dimensions, density, homogeneity, integrity, axial and circumferential surface cracks, cylindrical surface chips, pellets ends, cleanliness and workmanship, identification, and irradiation stability) requirements.
SCOPE
1.1 This specification is for finished sintered gadolinium oxide-uranium dioxide pellets for use in light-water reactors. It applies to gadolinium oxide-uranium dioxide pellets containing uranium of any  235U concentration and any concentration of gadolinium oxide.  
1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for gadolinium oxide-uranium dioxide pellets made from commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unirradiated uranium. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.  
1.3 This specification does not include (1) provisions for preventing criticality accidents or (2) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all international, federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. Examples of U.S. Governmental documents are Code of Federal Regulations (Latest Edition), Title 10, Part 50, Title 10, Part 71, and Title 49, Part 173.  
1.4 The following precautionary caveat pertains only to the technical requirements portion, Section 4, of this specification: This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This specification covers nuclear grade uranium metal that has either been processed through an enrichment plant, or has been produced by the blending of highly enriched uranium with other uranium, to obtain uranium of any 235U concentration below 20 % (and greater than 15 %) and that is intended for research reactor fuel fabrication. The uranium content of commercial grade enriched uranium metal shall be greater than or equal to 99.85 weight percent. The isotopic requirements for enriched uranium metal are presented in details. The chemical and isotopic composition shall be tested to meet the requirements prescribed.
SCOPE
1.1 This specification covers nuclear grade uranium metal that has either been processed through an enrichment plant, or has been produced by the blending of highly enriched uranium with other uranium, to obtain uranium of any  235U concentration below 20 % (and greater than 15 %) and that is intended for research reactor fuel fabrication. The scope of this specification includes specifications for enriched uranium metal derived from commercial natural uranium, recovered uranium, or highly enriched uranium. Commercial natural uranium, recovered uranium and highly enriched uranium are defined in Section 3. The objectives of this specification are to define the impurity and uranium isotope limits for commercial grade enriched uranium metal.  
1.2 This specification is intended to provide the nuclear industry with a standard for enriched uranium metal which is to be used in the production of research reactor fuel. In addition to this specification, the parties concerned may agree to other appropriate conditions.  
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this standard does not relieve the user of the obligation to conform to all applicable international, federal, state, and local regulations for processing, shipping, or any other way of using uranium metal (see, for example, C996 regarding references).

ABSTRACT
This specification covers uranium ore concentrate. Chemical composition shall have a minimum content requirement for uranium and a limited content for uranium isotope, insoluble uranium, extractable organic, and impurities. Uranium ore shall also conform to chemical analyses, particle size, flow ability, and foreign matter contents according to the specification. Standard packaging requirements for uranium ore shall also be met according to the specification.
SCOPE
1.1 This specification covers uranium ore concentrate containing a minimum of 65 mass % uranium.  
1.2 This specification does not include requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, national, state, and local regulations pertaining to possessing, shipping, or using source nuclear material (see 2.2).  
1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

ABSTRACT
This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
SCOPE
1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight (that is, 0.15 g Pu / g (U+Pu+Am)).  
1.2 Pellets produced under this specification are available in four grades.  
1.2.1 Grade R—240Pu content of (Pu+Am) (that is, g  240Pu / g (Pu+Am)) is at least 19 %.  
1.2.2 Grade F—240Pu content of (Pu+Am) is at least 7 % and less than 19 %.  
1.2.3 Grade N1—240Pu content of (Pu+Am) is less than 7 %.  
1.2.4 Grade N2—240Pu /239Pu does not exceed 0.10.  
1.3 This specification does not include (1) provisions for preventing criticality accidents or (2) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50—Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71—Packaging and Transportation of Radioactive Material; and Code of Federal Regulations Title 49, Part 173—General Requirements for Shipments and Packaging.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 The following safety hazards caveat pertains only to the technical requirements portion, Section 4, of this specification: This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
5.1 Uranium hexafluoride is normally produced and handled in large (typically 1 to 14-ton) quantities and must, therefore, be characterized by reference to representative samples (see ISO/DIS 7195). The samples are used to determine compliance with the applicable commercial specifications C996 and C787. The quantities involved, physical properties, chemical reactivity, and hazardous nature of UF6 are such that for representative sampling, specially designed equipment must be used and operated in accordance with the most carefully controlled and stringent procedures. This practice can be used by UF6 converters, enrichers, and fuel fabricators to review the effectiveness of existing procedures or as a guide to the design of equipment and procedures for future use.  
5.2 The intention of this practice is to avoid liquid UF6 sampling once the cylinder has been filled. For safety reasons, manipulation of large quantities of liquid UF6 should be avoided when possible.  
5.3 It is emphasized that this practice is not meant to address conventional or nuclear criticality safety issues.
SCOPE
1.1 This practice covers methods for withdrawing representative sample(s) of uranium hexafluoride (UF6) during a transfer occurring in the gas phase. Such transfer in the gas phase can take place from a mother cylinder, for example in an autoclave to a receiving cylinder. It can also occur during the filling in the gas phase of a cylinder during a continuous production process, for example centrifuge enrichment facility or the distillation column in a conversion facility. Such sample(s) may be used for determining compliance with the applicable commercial specification, for example Specification C996 or Specification C787.  
1.2 Since UF6 sampling is taken during the filling process, this practice does not address any special additional arrangements that may be agreed upon between the buyer and the seller when the sampled bulk material is being added to residues already present in a container (“heels recycle”). Such arrangements will be based on QA procedures such as traceability of cylinder origin (to prevent for example contamination with irradiated material).  
1.3 If the receiving cylinder is purged after filling and sampling, special verifications must be performed by the user to verify the representativity of the sample(s). It is then expected that the results found on volatile impurities with gas phase sampling may be conservative.  
1.4 This practice is only applicable when the transfer occurs in the gas phase. When the transfer is performed in the liquid phase, Practice C1052 should apply. This practice does not apply to gas sampling after the cylinder has been filled since the sample taken will not be representative of the cylinder.  
1.5 The scope of this practice does not include provisions for preventing criticality incidents.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This specification covers uranium ore concentrate. Chemical composition shall have a minimum content requirement for uranium and a limited content for uranium isotope, insoluble uranium, extractable organic, and impurities. Uranium ore shall also conform to chemical analyses, particle size, flow ability, and foreign matter contents according to the specification. Standard packaging requirements for uranium ore shall also be met according to the specification.
SCOPE
1.1 This specification covers uranium ore concentrate containing a minimum of 65 mass % uranium.
1.2 This specification does not include requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, national, state, and local regulations pertaining to possessing, shipping, or using source nuclear material (see 2.2).
1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

ABSTRACT
This specification covers sintered uranium dioxide pellets containing 235U for use in nuclear reactors. Chemical requirements include uranium content, impurity content, stoichiometry, and moisture content. Maximum concentration limits are specified for impurity elements such as: aluminum, carbon, calcium+magnesium, chlorine, chromium, cobalt, fluorine, hydrogen, iron, nickel, nitrogen, silicon, and thorium. Chemical analyses shall be performed. Nuclear requirements include isotopic content and equivalent boron content. The following are physical characteristics of the material: dimensions, pellet density, grain size and pore morphology, pellet integrity–surface cracks and chips, and cleanliness and workmanship. Fuel pellet irradiation stability shall be estimated. Pellet lot shall be retained throughout processing without mixing with other established lots.
SCOPE
1.1 This specification is for finished sintered uranium dioxide pellets. It applies to uranium dioxide pellets containing uranium of any  235U concentration for use in nuclear reactors.
1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for uranium dioxide pellets made from commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unirradiated uranium. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.  
1.3 This specification does not include  (a) provisions for preventing criticality accidents or  (b) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. Examples of U.S. Government documents are Code of Federal Regulations (Latest Edition), Title 10, Part 50, Title 10, Part 71, and Title 49, Part 173.
1.4 The following precautionary caveat pertains only to the technical requirements portion, Section 4, of this specification: This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability or regulatory limitations prior to use.

ABSTRACT
This specification covers uranium hexafluoride intended for feeding to an enrichment plant. Plants preparing uranium hexafluoride will have to control the purity of process chemicals and also employ low corrosion equipment to be successful in meeting the specifications for most impurities. Chemical and isotopic analysis of the material shall conform to the requirements prescribed.
SCOPE
1.1 This specification covers uranium hexafluoride (UF6) intended for feeding to an enrichment plant. Included are specifications for UF6 derived from unirradiated natural uranium and UF6 derived from irradiated uranium that has been reprocessed and converted to UF6 for enrichment and subsequent reuse. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Commercial Natural UF6 feedstock so that the corresponding enriched uranium is essentially equivalent to enriched uranium made entirely from virgin natural UF6; and ( 2) To define additional limits for Reprocessed UF6 (or any mixture of Reprocessed UF6 and Commercial Natural UF6). For such UF6, special provisions may be needed to ensure that no extra hazard arises to the work force, process equipment, or the environment.
1.2 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, federal, state, and local regulations for processing, shipping, or in any other way using UF6 (see, for example, TID-7016, DP-532, ORNL-NUREG-CSD-6, and DOE O 474.1).
1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

ABSTRACT
This specification covers sinterable nuclear-grade plutonium dioxide powders obtained by the oxalate precipitation route, calcination, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium, or recycled plutonium mixed with uranium. The material shall conform to required chemical compositions of plutonium, uranium, americium, impurities (boron, cadmium, carbon, chlorine, chromium, fluorine, iron, gadolinium, nickel, nitride nitrogen, and thorium), equivalent boron, and gamma activity. Materials shall also adhere to physical property requirements as to cleanliness and workmanship, particle size, and surface area.
SCOPE
1.1 This specification covers nuclear grade plutonium dioxide, sinterable powder obtained by the oxalate precipitation route, calcined above 500°C, or any other equivalent process acceptable to the buyer. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural or slightly enriched uranium or by in-reactor neutron irradiation of recycled plutonium mixed with uranium.
1.2 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all national and local regulations on processing, shipping, or using source or special nuclear materials. For examples in the U.S. Government, relevant documents are Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-7016 , and “Handbook of Nuclear Safety”, H. K. Clark, U.S. Atomic Energy Commission Report, DP-532 .
1.3 The PuO2 shall be produced by a qualified process and in accordance with a quality assurance program approved by the user.
1.4 The values stated in SI units are to be regarded as the standard.
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This specification covers nuclear grade uranium hexafluoride (UF6) that has been processed through an enrichment plant or produced by blending highly enriched uranium with other uranium to produce a concentration suitable for nuclear fuel fabrication. This specification defines the impurity and uranium isotope limits for the enriched commercial grade UF6 and for enriched reprocessed UF6. All materials should conform to the specified chemical, physical, and isotopic requirements.
SCOPE
1.1 This specification covers nuclear grade uranium hexafluoride (UF6) that either has been processed through an enrichment plant, or has been produced by the blending of Highly Enriched Uranium with other uranium to obtain uranium of any  235U concentration below 5 % and that is intended for fuel fabrication. The objectives of this specification are twofold: (1) To define the impurity and uranium isotope limits for Enriched Commercial Grade UF6 so that, with respect to fuel design and manufacture, it is essentially equivalent to enriched uranium made from natural UF6; and (2) To define limits for Enriched Reprocessed UF6 to be expected if Reprocessed UF6 is to be enriched without dilution with Commercial Natural UF6. For such UF6, special provisions, not defined herein, may be needed to ensure fuel performance and to protect the work force, process equipment, and the environment.  
1.2 This specification is intended to provide the nuclear industry with a standard for enriched UF6 that is to be used in the production of sinterable UO2 powder for fuel fabrication. In addition to this specification, the parties concerned may agree to other appropriate conditions.
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all applicable international, federal, state, and local regulations for processing, shipping, or in any other way using UF6  (see, for example, TID-7016, DP-532, and DOE O474.1).
1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

SCOPE
1.1 This specification covers uranium oxides, including processed byproducts or scrap material (powder, pellets, or pieces), that are intended for dissolution into uranyl nitrate solution meeting the requirements of Specification C788 prior to conversion into nuclear grade UO2 powder with a  235U content of less than 5 %. This specification defines the impurity and uranium isotope limits for such urania powders that are to be dissolved prior to processing to nuclear grade UO2 as defined in Specification C753.
1.2 This specification provides the nuclear industry with a general standard for such uranium oxide powders. It recognizes the diversity of conversion processes and the processes to which such powders are subsequently to be subjected (for instance, by solvent extraction). It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between the buyer and seller.
1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, national, state and local regulations for processing, shipping, or any other way of using urania powders (see 2.2 and 2.3).

ABSTRACT
These practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples from uranium-ore concentrates (UOC) and for obtaining a series of representative secondary samples from the original bulk sample for the determination of moisture and other test purposes, and for the preparation of pulverized analytical samples. These practices consist of a number of alternative procedures for (1) primary sampling such as one-stage falling stream, two-stage falling stream, and Auger sampling; (2) secondary sampling such as straight-path (reciprocating) cutter sampling and rotating (Vezin) cutter multi-sampling; (3) sample preparation such as concurrent-drying, natural moisture, and calcination; and (4) sample packaging such as wax sealing and vacuum sealing. These procedures do not include requirements for health, safety, and accountability. The material and sampling equipment requirements are detailed. Schematic diagrams of the primary and secondary samplers are provided.
SCOPE
1.1 These practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples from uranium-ore concentrates (UOC) (see Specification C967).  
1.2 These practices also provide for obtaining a series of representative secondary samples from the original bulk sample for the determination of moisture and other test purposes, and for the preparation of pulverized analytical samples (see Test Methods C1022).  
1.3 These practices consist of a number of alternative procedures for sampling and sample preparation which have been shown to be satisfactory through long experience in the nuclear industry. These procedures are described in the following order.
Stage ProcedureSection   Primary SamplingOne-stage falling stream4   Two-stage falling stream5   Auger6  Secondary SamplingStraight-path (reciprocating)7   Rotating (Vezin)8, 9  Sample Preparation10   Concurrent-drying11-13   Natural moisture14-16  Calcination17, 18  Sample Packaging19   Wax sealing20   Vacuum sealing21  
1.3.1 The primary and secondary sampling stages can be organized in the following way:
1.3.2 It is possible to combine the various elements of these stages in different ways to give satisfactory results depending on the agreed requirements of the contracting parties. For a given stage, however, each procedure must be regarded as a whole. It is highly inadvisable to mix elements belonging to different procedures.
1.4 These procedures do not include requirements for health, safety, and accountability. The observance of these practices does not relieve the user of the obligation to be aware of and to conform to all applicable international, federal, state, and local regulations pertaining to processing, shipping, or using uranium-ore concentrates. (Guidance is provided in CFR 10, Chapter 1.)
1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.6 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This practice details the recommended method for calculating the equivalent boron content (EBC) values of nuclear elements and materials that are of potential significance as thermal neutron poisons. EBC factors are determined from the atomic weight of elements and the thermal neutron absorption cross section in barns. These may be used depending upon the actual neutron energy characteristics of the applicable reactor system. The elements aluminum, fluorine, rubidium, barium, lead, silicon, beryllium, neon, tin, bismuth, oxygen, zirconium, carbon, magnesium, cerium, and phosphorus are not required to be included in the EBC calculations as their contribution to the total poison effect is not considerably significant.
SCOPE
1.1 This standard details a recommended practice for the calculation of the Equivalent Boron Content (EBC) for nuclear materials. The EBC is used to provide a measure of the macroscopic neutron absorption cross section of a nuclear material. EBC factors for the natural elements are determined from their atomic their masses and thermal neutron absorption cross sections. This practice is illustrated by using EBC factors that are based on thermal neutron (2200 m/s) absorption cross sections. Other EBC factors may be used depending upon the actual neutron energy spectrum.
1.2 The EBC is a characteristic of a homogeneous material. Characterization of inhomogeneous materials and calculation of neutron multiplication factors require techniques that are beyond the scope of this practice.  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

ABSTRACT
This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5% 235U intended for subsequent manufacture into either UF6 or direct conversion to uranium oxide. This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or crystals. The purpose of this specification is: to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate).
SCOPE
1.1 This specification applies to nuclear-grade aqueous uranyl nitrate solution or crystals not exceeding 5 %  235U intended for subsequent manufacture into either UF6  (for feed to an enrichment plant) or direct conversion to uranium oxide (for use in reactors).
1.2 This specification is intended to provide the nuclear industry with a general standard for aqueous uranyl nitrate solution or crystals. It recognizes the diversity of manufacturing methods and the processes to which it is subsequently to be subjected. It is therefore anticipated that it may be necessary to include supplementary specification limits by agreement between purchaser and manufacturer. Different limits are appropriate depending on whether or not the uranyl nitrate is to be converted to UF6  for subsequent processing.
1.3 The purpose of this specification is: (a) to define the impurity and uranium isotope limits for commercial standard uranyl nitrate, and (b) to define additional limits for reprocessed uranyl nitrate (or any mixture of reprocessed and commercial standard uranyl nitrate). For such uranyl nitrates, special provisions may need to be made to ensure that no extra hazard arises to the employees, the process equipment, or the environment.
1.4 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this standard does not relieve the user of the obligation to conform to all international, federal, state and local regulations for processing, shipping, or any other way of using the uranyl nitrate. An example of a U.S. Government Document is the Code of Federal Regulations, Title 10, Part 50 (latest edition).
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

ABSTRACT
This specification covers nuclear-grade, sinterable uranium dioxide (UO2) powder and applies to uranium dioxide powder containing uranium of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors. This specification refers expressly to calcined UO2 powder before the addition of any die lubricant, binder, or pore former, and defines isotopic limits for commercial grade UO2 so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed uranium and. Provisions for preventing criticality accidents or requirements for health and safety are not included in this specification. The powder shall conform to the specified chemical requirements including uranium content, oxygen-to-uranium ratio, impurity content (such as aluminum, carbon, calcium and magnesium, chlorine, fluorine, iron, lead, manganese, molybdenum, nickel, nitrogen, phosphorus, silicon, tantalum, thorium, tin, titanium, tungsten, vanadium, and zinc), moisture content, isotopic content, equivalent boron content, and cleanliness and workmanship. The powder shall also meet the specified physical requirements including particle size, bulk density, and sinterability. Sampling requirements for the test specimen and the test methods for chemical analysis and acceptance testing are detailed.
SCOPE
1.1 This specification covers nuclear-grade, sinterable uranium dioxide (UO2) powder. It applies to uranium dioxide powder containing uranium of any 235U concentration in the production of nuclear fuel pellets for use in nuclear reactors.
1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed uranium. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.
1.3 This specification does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material.
1.4 This specification refers expressly to calcined UO2 powder before the addition of any die lubricant, binder, or pore former. If powder is sold with such additions or prepared as press feed, sampling procedures, allowable impurity contents, or powder physical requirements may need to be modified by agreement between the buyer and the seller.
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory requirements prior to use.

ABSTRACT
This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
SCOPE
1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. This specification may not completely cover the requirements for pellets fabricated from weapons-derived plutonium.
1.2 This specification does not include (1) provisions for preventing criticality accidents or (2) requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50Domestic Licensing of Production and Utilization Facilities; Code of Federal Regulations Title 10, Part 71Packaging and Transportation of Radioactive Material; and Code of Federal Regulations Title 49, Part 173General Requirements for Shipments and Packaging.
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.4 The following safety hazards caveat pertains only to the technical requirements portion, Section 4, of this specification: This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.