C26.03 - Neutron Absorber Materials Specifications

ABSTRACT
This specification covers the properties and requirements for pellets of stabilized cubic hafnium oxide used in nuclear reactors. Hafnium oxide should consist of a stabilizing agent, the recommended of which is yttrium oxide, though others such as calcium oxide and magnesium oxide may also be used as agreed upon by the buyer and seller. The material shall meet specified values of the following requirements: physical dimensions; density; mechanical properties; phase stabilization; impurity concentration limits; moisture concentration limit; visual appearance; end and circumferential chips; cracks; and fissures and other defects.
SCOPE
1.1 This specification applies to pellets of stabilized cubic hafnium oxide used in nuclear reactors.  
1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.3 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 defines the physical and chemical requirements for hafnium oxide powder intended for fabrication into shapes for use in a nuclear reactor core.  
1.2 The material described herein shall be particulate in nature.  
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.

SCOPE
1.1 This specification defines the physical and chemical requirements for zirconium oxide powder intended for fabrication into shapes, either entirely or partially of zirconia, for use in a nuclear reactor core.  
1.2 The material described herein shall be particulate in nature.  
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 applies to pellets of stabilized zirconium oxide used in nuclear reactors. The chemical composition requirements such as the stabilizing additive (calcium oxide or yttrium oxide), analytical chemistry methods, impurity concentration (including hafnium, boron, gadolinium, samarium, europium, dysprosium, cobalt, silicon, iron, calcium, magnesium, aluminum, titanium, thorium, fluorine, chlorine, bromine, iodine, and hydrogen), and moisture concentration are prescribed. The nuclear grade pellets shall conform to the specified physical requirements which includes the following: physical dimensions, density, mechanical properties and test methods such as compressive test and thermal cycling test, and visual appearance such as end chips, circumferential chips, cracks, and fissures. The requirements for cleanliness before and after sampling and packaging are given.
SCOPE
1.1 This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors.  
1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.3 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 provides the chemical and physical properties and requirements for nuclear-grade aluminum oxide powder intended for fabrication into shapes for nuclear applications. The materials shall conform to physical requirements as to particle size distribution, and specific surface area, and chemical requirements as to loss-on-ignition, and total and elemental concentrations of all impurities. Impurities may include silicaon, iron-chromium-nickel, magnesium, sodium, calcium, hafnium, fluorine, fluorine-chlorine-iodine-bromine, gadolinium, samarium, europium, and dysprosium.
SCOPE
1.1 This specification provides the chemical and physical requirements for nuclear-grade aluminum oxide powder intended for fabrication into shapes for nuclear applications. Two specific uses for which this powder is intended are Al2O3  pellets and Al2O3 − B4C composite pellets for use as thermal insulator or burnable neutron absorbers, respectively.  
1.2 The material described herein shall be particulate in nature.  
1.3 Units—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.

SCOPE
1.1 This specification applies to pellets of aluminum oxide that may be ultimately used in a reactor core, for example, as filler or spacers within fuel, burnable poison, or control rods. In order to distinguish between the subject pellets and “burnable poison” pellets, it is established that the subject pellets are not intended to be used as neutron-absorbing material.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.3 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 storage of nuclear fuel in high-density storage racks is dependent upon the functionality and integrity of an absorber between the stored fuel assemblies to ensure that the reactivity of the storage configuration does not exceed the K-effective allowed by applicable regulations. A confirmation test may be required to verify the functionality and integrity of the absorber within the racks. If establishing a surveillance program for newly installed or existing absorber material in fuel racks, the following methods are suggested: (a) coupon monitoring program (if coupons are available), (b) in-situ neutron attenuation test, and (c) other applicable in-situ tests such as visual inspection or drag test.  
4.2 This guide provides guidance for establishing and conducting a surveillance program for monitoring the ongoing functionality and integrity of the absorbers.
SCOPE
1.1 This guide provides guidance for establishing a surveillance test program to monitor the performance of boron-based neutron absorbing material systems (absorbers) necessary to maintain sub-criticality in nuclear fuel storage racks in a pool environment. The practices presented in this guide, when implemented, will provide a comprehensive surveillance test program to verify the functionality and integrity of the neutron absorbing material within the storage racks. The performance of a surveillance test program provides added assurance of the safe and effective operation of a high-density storage facility for nuclear fuel. There are several different techniques for surveillance testing of boron-based neutron absorbing materials. This guide focuses on coupon monitoring and in-situ testing.  
1.2 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.  
1.3 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 defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.  
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.  
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron enriched in boron-10 could also be used.  
1.4 The materials systems described herein shall be functional (that is, always be capable to maintain a boron-10 areal density such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool).  
1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.  
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
4.1 For criticality control of nuclear fuel in dry storage and transportation, the most commonly used neutron absorber materials are borated stainless steel alloys, borated aluminum alloys, and boron carbide aluminum alloy composites. The boron used in these neutron absorber materials may be natural or enriched in the nuclide 10B. The boron is usually incorporated either as an intermetallic phase (for example, AlB2, TiB2, CrB2, etc.) in an aluminum alloy or stainless steel, or as a stable chemical compound particulate such as boron carbide (B4C), typically in an aluminum MMC or cermet.  
4.2 While other neutron absorbers continue to be investigated, 10B has been most widely used in these applications, and it is the only thermal neutron absorber addressed in this standard.  
4.3 In service, many neutron absorber materials are inaccessible and not amenable to a surveillance program. These neutron absorber materials are often expected to perform over an extended period.  
4.4 Qualification and acceptance procedures demonstrate that the neutron absorber material has the necessary characteristics to perform its design functions during the service lifetime.  
4.5 The criticality control function of neutron absorber materials in dry cask storage systems and transportation packagings is only significant in the presence of a moderator, such as during loading of fuel under water, or water ingress resulting from hypothetical accident conditions.  
4.6 The expected users of this standard include designers, neutron absorber material suppliers and purchasers, government agencies, consultants and utility owners. Typical use of the practice is to summarize practices which provide input for design specification, material qualification, and production acceptance. Adherence to this standard does not guarantee regulatory approval; a government regulatory authority may require different tests or additional tests, and may impose limits or restrictions on the use of a neutron absorbe...
SCOPE
1.1 This practice provides procedures for qualification and acceptance of neutron absorber materials used to provide criticality control by absorbing thermal neutrons in systems designed for nuclear fuel storage, transportation, or both.  
1.2 This practice is limited to neutron absorber materials consisting of metal alloys, metal matrix composites (MMCs), and cermets, clad or unclad, containing the neutron absorber boron-10 (10B).  
1.3 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.  
1.4 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
3.1 Silver-indium-cadmium alloy is used as a control material in nuclear reactors. In order to be suitable for this purpose, the material must meet the specifications for assay and impurity content. These test methods are designed to show whether or not a given material meets the specifications as given in Specification C752.  
3.1.1 An assay is performed to determine whether the material has the chemical composition specified.  
3.1.2 The impurity content is determined to ensure that the maximum concentration limit of impurities is not exceeded.
SCOPE
1.1 These test methods cover procedures for the chemical and spectrochemical analysis of nuclear grade silver-indium-cadmium (Ag-In-Cd) alloys to determine compliance with specifications.  
1.2 The analytical procedures appear in the following order:    
Sections  
Silver, Indium, and Cadmium by a Titration Method  
7 – 15  
Trace Impurities by Carrier-Distillation Spectro-
chemical Method  
16 – 22  
1.3 The values stated in SI units are to be regarded as the 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. For specific hazard and precautionary statements, see Section 5 and Practices E50.  
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 applies to composite pellets composed of mixtures of nuclear-grade aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods. Specimens shall be sampled and tested as appropriate, and shall adhere accordingly to required chemical compositions, physical dimensions, density, boron carbide homogeneity, mechanical properties, visual appearance, end and circumferential chips, cracks, and fissures and other defects.
SCOPE
1.1 This specification applies to pellets composed of mixtures of aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods.  
1.2 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.  
1.3 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 applies to boron carbide pellets for use as a control material in nuclear reactors.  
1.2 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.  
1.3 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 Aluminum oxide pellets are used in a reactor core as filler or spacers within fuel, burnable poison, or control rods. In order to be suitable for this purpose, the material must meet certain criteria for impurity content. These test methods are designed to show whether or not a given material meets the specifications for these items as described in Specification C785.  
4.1.1 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.  
4.2 Aluminum oxide-boron carbide composite pellets are used in a reactor core as a component in neutron absorber rods. In order to be suitable for this purpose, the material must meet certain criteria for boron content, isotopic composition, and impurity content as described in Specification C784.  
4.2.1 The material is assayed for boron to determine whether the boron content is as specified by the purchaser.  
4.2.2 Determination of the isotopic content of the boron is made to establish whether the 10B concentration is in compliance with the purchaser's specifications.  
4.2.3 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.
SCOPE
1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade aluminum oxide and aluminum oxide-boron carbide composite pellets to determine compliance with specifications.  
1.2 The analytical procedures appear in the following order:    
Sections  
Boron by Titrimetry and ICP OES  
8 to 17  
Separation of Boron for Mass Spectrometry  
18 to 23  
Isotopic Composition by Mass Spectrometry  
24 to 27  
Separation of Halides by Pyrohydrolysis  
28 to 31  
Chloride and Fluoride by Ion-Selective Electrode  
32 to 34  
Chloride, Bromide, and Iodide by Amperometric Microtitrimetry  
35 to 37  
Trace Elements by Emission Spectroscopy  
38 to 50  
Keywords  
51  
1.3 The values stated in SI units are to be regarded as the 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. (For specific precautionary statements, see Section 6.)  
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 Boron carbide is used as a control material in nuclear reactors. In order to be suitable for this purpose, the material must meet certain criteria for assay, isotopic composition, and impurity content. These methods are designed to show whether or not a given material meets the specifications for these items as described in Specifications C750 and C751.  
4.1.1 An assay is performed to determine whether the material has the specified boron and carbon content.  
4.1.2 Determination of the isotopic content of the boron and the free carbon content is made to establish whether the content is in compliance with the purchaser’s specifications.  
4.1.3 Impurity content is determined to ensure that the maximum concentration limit of certain impurities (chloride, fluoride, water, metallic impurities, soluble boron) is not exceeded.
SCOPE
1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade boron carbide powder and pellets to determine compliance with specifications.  
1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.3 The analytical procedures appear in the following order:    
Sections  
Total Carbon by Combustion in an Inductive Furnace and
Infrared Measurement  
8 – 17  
Total Boron by Titrimetry and ICP OES  
18 – 28  
Isotopic Composition by Mass Spectrometry  
29 – 33  
Pyrohydrolysis  
34 – 41  
Chloride by Constant-Current Coulometry  
42 – 50  
Chloride and Fluoride by Ion-Selective Electrode  
51 – 59  
Water by Constant-Voltage Coulometry and Weight Loss on
Drying  
60 – 63  
Metallic Impurities by DCArc OES and wet chemical methods  
64 and 65  
Soluble Boron by Titrimetry and ICP OES  
66 – 80  
Free Carbon by a Coulometric Method  
81 – 90  
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 silver-indium-cadmium alloy for use as a control material in light-water nuclear reactors. The use of this material in applications is excluded where material strength of this alloy is a prime requisite. Also, this material must be protected from the primary water by a corrosion and wear resistant cladding. The identity of each lot by melt number shall be maintained at all stages of manufacture. Parts produced to this specification shall be made from billets by hot working and cold finishing to size. The cold-finished parts shall be produced to the finish condition and dimensions as specified. The surface of the cold-finished part shall be free of oxides, grease, oil, residual lubricants, inclusions, and other extraneous materials. Surface defects such as folds, cracks, seams, slivers, and blisters shall be cause for rejection.
SCOPE
1.1 This specification covers silver-indium-cadmium alloy for use as a control material in light-water nuclear reactors.  
1.2 The scope of this specification excludes the use of this material in applications where material strength of this alloy is a prime requisite. Also, this material must be protected from the primary water by a corrosion and wear resistant cladding.  
1.3 The values stated in SI units are to be regarded as 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 provides chemical and physical requirements for nuclear-grade gadolinium oxide powder intended for subsequent processing and use in nuclear fuel applications. Chemical requirements of the specification include loss-on-ignition, gadolinium oxide concentration, and impurity content limits. The buyer shall specify the particle size, density, shape factor, and crystal structure. Gadolinium oxide powder shall be packaged in sealed containers.
SCOPE
1.1 This specification provides the chemical and physical requirements for nuclear-grade gadolinium oxide powder intended for subsequent processing and use in nuclear fuel applications, for example, as an addition to uranium dioxide.  
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 comply with all federal, state, and local regulations pertaining to possessing, shipping, processing, or using this material.  
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 defines the chemical and physical requirements for boron carbide powder intended for a variety of nuclear applications. The powder shall be classified as: Type 1; Type 2; and Type 3. The material shall conform to the chemical composition requirements prescribed. Quality control tests, acceptance tests, referee tests, and retention of archive samples by the seller shall be performed to conform to the specified requirements.
SCOPE
1.1 This specification defines the chemical and physical requirements for boron carbide powder intended for a variety of nuclear applications. Because each application has a different need for impurity and boron requirements, three different chemical compositions of powder are specified. In using this specification, it is necessary to dictate which type of powder is intended to be used. In general, the intended applications for the various powder types are as follows:  
1.1.1 Type 1—For use as particulate material in nuclear reactor core applications.  
1.1.2 Type 2—Powder that will be further processed into a fabricated shape for use in a nuclear reactor core or used in non-core applications when the powder directly or indirectly may cause adverse effects on structural components, such as halide stress corrosion of stainless steel.  
1.1.3 Type 3—Powder that will be used for non-core applications or special in-core applications.  
1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.3 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 defines the physical and chemical requirements of nuclear-grade beryllium oxide (BeO) powder to be used in fabricating nuclear components.  
1.2 This specification does not include requirements for health and safety (1-5).2 It recognizes the material as a Class B poison and suggests that producers and users become thoroughly familiar with and comply to applicable federal, state, and local regulations and handling guidelines (1).  
1.3 Special tests and procedures are given in Annex A1 and Annex A2.  
1.4 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
4.1 The storage of nuclear fuel in high-density storage racks is dependent upon the functionality and integrity of an absorber between the stored fuel assemblies to ensure that the reactivity of the storage configuration does not exceed the K-effective allowed by applicable regulations. A confirmation test may be required to verify the functionality and integrity of the absorber within the racks. If establishing a surveillance program for newly installed or existing absorber material in fuel racks, the following methods are suggested: (a) coupon monitoring program (if coupons are available), (b) in-situ neutron attenuation test, and (c) other applicable in-situ tests such as visual inspection or drag test.  
4.2 This guide provides guidance for establishing and conducting a surveillance program for monitoring the ongoing functionality and integrity of the absorbers.
SCOPE
1.1 This guide provides guidance for establishing a surveillance test program to monitor the performance of boron-based neutron absorbing material systems (absorbers) necessary to maintain sub-criticality in nuclear fuel storage racks in a pool environment. The practices presented in this guide, when implemented, will provide a comprehensive surveillance test program to verify the functionality and integrity of the neutron absorbing material within the storage racks. The performance of a surveillance test program provides added assurance of the safe and effective operation of a high-density storage facility for nuclear fuel. There are several different techniques for surveillance testing of boron-based neutron absorbing materials. This guide focuses on coupon monitoring and in-situ testing.  
1.2 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.  
1.3 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 defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.  
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.  
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron enriched in boron-10 could also be used.  
1.4 The materials systems described herein shall be functional (that is, always be capable to maintain a boron-10 areal density such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool).  
1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.  
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
4.1 For criticality control of nuclear fuel in dry storage and transportation, the most commonly used neutron absorber materials are borated stainless steel alloys, borated aluminum alloys, and boron carbide aluminum alloy composites. The boron used in these neutron absorber materials may be natural or enriched in the nuclide 10B. The boron is usually incorporated either as an intermetallic phase (for example, AlB2, TiB2, CrB2, etc.) in an aluminum alloy or stainless steel, or as a stable chemical compound particulate such as boron carbide (B4C), typically in an aluminum MMC or cermet.  
4.2 While other neutron absorbers continue to be investigated, 10B has been most widely used in these applications, and it is the only thermal neutron absorber addressed in this standard.  
4.3 In service, many neutron absorber materials are inaccessible and not amenable to a surveillance program. These neutron absorber materials are often expected to perform over an extended period.  
4.4 Qualification and acceptance procedures demonstrate that the neutron absorber material has the necessary characteristics to perform its design functions during the service lifetime.  
4.5 The criticality control function of neutron absorber materials in dry cask storage systems and transportation packagings is only significant in the presence of a moderator, such as during loading of fuel under water, or water ingress resulting from hypothetical accident conditions.  
4.6 The expected users of this standard include designers, neutron absorber material suppliers and purchasers, government agencies, consultants and utility owners. Typical use of the practice is to summarize practices which provide input for design specification, material qualification, and production acceptance. Adherence to this standard does not guarantee regulatory approval; a government regulatory authority may require different tests or additional tests, and may impose limits or restrictions on the use of a neutron absorbe...
SCOPE
1.1 This practice provides procedures for qualification and acceptance of neutron absorber materials used to provide criticality control by absorbing thermal neutrons in systems designed for nuclear fuel storage, transportation, or both.  
1.2 This practice is limited to neutron absorber materials consisting of metal alloys, metal matrix composites (MMCs), and cermets, clad or unclad, containing the neutron absorber boron-10 (10B).  
1.3 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.  
1.4 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 provides the chemical and physical properties and requirements for nuclear-grade aluminum oxide powder intended for fabrication into shapes for nuclear applications. The materials shall conform to physical requirements as to particle size distribution, and specific surface area, and chemical requirements as to loss-on-ignition, and total and elemental concentrations of all impurities. Impurities may include silicaon, iron-chromium-nickel, magnesium, sodium, calcium, hafnium, fluorine, fluorine-chlorine-iodine-bromine, gadolinium, samarium, europium, and dysprosium.
SCOPE
1.1 This specification provides the chemical and physical requirements for nuclear-grade aluminum oxide powder intended for fabrication into shapes for nuclear applications. Two specific uses for which this powder is intended are Al2O3  pellets and Al2O3 − B4C composite pellets for use as thermal insulator or burnable neutron absorbers, respectively.  
1.2 The material described herein shall be particulate in nature.

SCOPE
1.1 This specification applies to boron carbide pellets for use as a control material in nuclear reactors.  
1.2 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 silver-indium-cadmium alloy for use as a control material in light-water nuclear reactors. The use of this material in applications is excluded where material strength of this alloy is a prime requisite. Also, this material must be protected from the primary water by a corrosion and wear resistant cladding. The identity of each lot by melt number shall be maintained at all stages of manufacture. Parts produced to this specification shall be made from billets by hot working and cold finishing to size. The cold-finished parts shall be produced to the finish condition and dimensions as specified. The surface of the cold-finished part shall be free of oxides, grease, oil, residual lubricants, inclusions, and other extraneous materials. Surface defects such as folds, cracks, seams, slivers, and blisters shall be cause for rejection.
SCOPE
1.1 This specification covers silver-indium-cadmium alloy for use as a control material in light-water nuclear reactors.  
1.2 The scope of this specification excludes the use of this material in applications where material strength of this alloy is a prime requisite. Also, this material must be protected from the primary water by a corrosion and wear resistant cladding.  
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 composite pellets composed of mixtures of nuclear-grade aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods. Specimens shall be sampled and tested as appropriate, and shall adhere accordingly to required chemical compositions, physical dimensions, density, boron carbide homogeneity, mechanical properties, visual appearance, end and circumferential chips, cracks, and fissures and other defects.
SCOPE
1.1 This specification applies to pellets composed of mixtures of aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods.  
1.2 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 defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.  
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.  
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron, enriched in boron-10 could also be used.  
1.4 The materials systems described herein shall be functional – that is always be capable to maintain a boron-10 areal density such that subcriticality is maintained depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool.  
1.5 Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.  
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.

SIGNIFICANCE AND USE
4.1 The storage of nuclear fuel in high-density storage racks is dependent upon the functionality and integrity of an absorber between the stored fuel assemblies to ensure that the reactivity of the storage configuration does not exceed the K-effective allowed by applicable regulations. A confirmation test may be required to verify the functionality and integrity of the absorber within the racks. If establishing a surveillance program for newly installed or existing absorber material in fuel racks, the following methods are suggested: (a) coupon monitoring program (if coupons are available); (b) in-situ neutron attenuation test; and (c) other applicable in-situ tests such as visual inspection or drag test.  
4.2 This guide provides guidance for establishing and conducting a surveillance program for monitoring the ongoing functionality and integrity of the absorbers.
SCOPE
1.1 This guide provides guidance for establishing a surveillance test program to monitor the performance of boron-based neutron absorbing material systems (absorbers) necessary to maintain sub-criticality in nuclear fuel storage racks in a pool environment. The practices presented in this guide, when implemented, will provide a comprehensive surveillance test program to verify the functionality and integrity of the neutron absorbing material within the storage racks. The performance of a surveillance test program provides added assurance of the safe and effective operation of a high-density storage facility for nuclear fuel. There are several different techniques for surveillance testing of boron-based neutron absorbing materials. This guide focuses on coupon monitoring and in-situ testing.  
1.2 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.

SCOPE
1.1 This specification defines the physical and chemical requirements for hafnium oxide powder intended for fabrication into shapes for use in a nuclear reactor core.  
1.2 The material described herein shall be particulate in nature.  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

SCOPE
1.1 This specification applies to pellets of aluminum oxide that may be ultimately used in a reactor core, for example, as filler or spacers within fuel, burnable poison, or control rods. In order to distinguish between the subject pellets and “burnable poison” pellets, it is established that the subject pellets are not intended to be used as neutron-absorbing material.  
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.

ABSTRACT
This specification covers the properties and requirements for pellets of stabilized cubic hafnium oxide used in nuclear reactors. Hafnium oxide should consist of a stabilizing agent, the recommended of which is yttrium oxide, though others such as calcium oxide and magnesium oxide may also be used as agreed upon by the buyer and seller. The material shall meet specified values of the following requirements: physical dimensions; density; mechanical properties; phase stabilization; impurity concentration limits; moisture concentration limit; visual appearance; end and circumferential chips; cracks; and fissures and other defects.
SCOPE
1.1 This specification applies to pellets of stabilized cubic hafnium oxide used in nuclear reactors.  
1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

SIGNIFICANCE AND USE
4.1 For criticality control of nuclear fuel in dry storage and transportation, the most commonly used neutron absorber materials are borated stainless steel alloys, borated aluminum alloys, and boron carbide aluminum alloy composites. The boron used in these neutron absorber materials may be natural or enriched in the nuclide 10B. The boron is usually incorporated either as an intermetallic phase (for example, AlB2, TiB2, CrB2, etc.) in an aluminum alloy or stainless steel, or as a stable chemical compound particulate such as boron carbide (B4C), typically in an aluminum MMC or cermet.  
4.2 While other neutron absorbers continue to be investigated, 10B has been most widely used in these applications, and it is the only thermal neutron absorber addressed in this standard.  
4.3 In service, many neutron absorber materials are inaccessible and not amenable to a surveillance program. These neutron absorber materials are often expected to perform over an extended period.  
4.4 Qualification and acceptance procedures demonstrate that the neutron absorber material has the necessary characteristics to perform its design functions during the service lifetime.  
4.5 The criticality control function of neutron absorber materials in dry cask storage systems and transportation packagings is only significant in the presence of a moderator, such as during loading of fuel under water, or water ingress resulting from hypothetical accident conditions.  
4.6 The expected users of this standard include designers, neutron absorber material suppliers and purchasers, government agencies, consultants and utility owners. Typical use of the practice is to summarize practices which provide input for design specification, material qualification, and production acceptance. Adherence to this standard does not guarantee regulatory approval; a government regulatory authority may require different tests or additional tests, and may impose limits or restrictions on the use of a neutron absorbe...
SCOPE
1.1 This practice provides procedures for qualification and acceptance of neutron absorber materials used to provide criticality control by absorbing thermal neutrons in systems designed for nuclear fuel storage, transportation, or both.  
1.2 This practice is limited to neutron absorber materials consisting of metal alloys, metal matrix composites (MMCs), and cermets, clad or unclad, containing the neutron absorber boron-10 (10B).  
1.3 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.

SCOPE
1.1 This specification defines the physical and chemical requirements for zirconium oxide powder intended for fabrication into shapes, either entirely or partially of zirconia, for use in a nuclear reactor core.  
1.2 The material described herein shall be particulate in nature.  
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
3.1 Silver-indium-cadmium alloy is used as a control material in nuclear reactors. In order to be suitable for this purpose, the material must meet the specifications for assay and impurity content. These test methods are designed to show whether or not a given material meets the specifications as given in Specification C752.  
3.1.1 An assay is performed to determine whether the material has the chemical composition specified.  
3.1.2 The impurity content is determined to ensure that the maximum concentration limit of impurities is not exceeded.
SCOPE
1.1 These test methods cover procedures for the chemical and spectrochemical analysis of nuclear grade silver-indium-cadmium (Ag-In-Cd) alloys to determine compliance with specifications.  
1.2 The analytical procedures appear in the following order:    
Sections  
Silver, Indium, and Cadmium by a Titration Method  
7 – 15  
Trace Impurities by Carrier-Distillation Spectro-
chemical Method  
16 – 22  
1.3 The values stated in SI units are to be regarded as the 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. For specific hazard and precautionary statements, see Section 5 and Practices E50.

ABSTRACT
This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors. The chemical composition requirements such as the stabilizing additive (calcium oxide or yttrium oxide), analytical chemistry methods, impurity concentration (including hafnium, boron, gadolinium, samarium, europium, dysprosium, cobalt, silicon, iron, calcium, magnesium, aluminum, titanium, thorium, fluorine, chlorine, bromine, iodine, and hydrogen), and moisture concentration are prescribed. The nuclear grade pellets shall conform to the specified physical requirements which includes the following: physical dimensions, density, mechanical properties and test methods such as compressive test and thermal cycling test, and visual appearance such as end chips, circumferential chips, cracks, and fissures. The requirements for cleanliness before and after sampling and packaging are given.
SCOPE
1.1 This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors.  
1.2 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 defines the chemical and physical requirements for boron carbide powder intended for a variety of nuclear applications. The powder shall be classified as: Type 1; Type 2; and Type 3. The material shall conform to the chemical composition requirements prescribed. Quality control tests, acceptance tests, referee tests, and retention of archive samples by the seller shall be performed to conform to the specified requirements.
SCOPE
1.1 This specification defines the chemical and physical requirements for boron carbide powder intended for a variety of nuclear applications. Because each application has a different need for impurity and boron requirements, three different chemical compositions of powder are specified. In using this specification, it is necessary to dictate which type of powder is intended to be used. In general, the intended applications for the various powder types are as follows:  
1.1.1 Type 1—For use as particulate material in nuclear reactor core applications.  
1.1.2 Type 2—Powder that will be further processed into a fabricated shape for use in a nuclear reactor core or used in non-core applications when the powder directly or indirectly may cause adverse effects on structural components, such as halide stress corrosion of stainless steel.  
1.1.3 Type 3—Powder that will be used for non-core applications or special in-core applications.  
1.2 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 provides chemical and physical requirements for nuclear-grade gadolinium oxide powder intended for subsequent processing and use in nuclear fuel applications. Chemical requirements of the specification include loss-on-ignition, gadolinium oxide concentration, and impurity content limits. The buyer shall specify the particle size, density, shape factor, and crystal structure. Gadolinium oxide powder shall be packaged in sealed containers.
SCOPE
1.1 This specification provides the chemical and physical requirements for nuclear-grade gadolinium oxide powder intended for subsequent processing and use in nuclear fuel applications, for example, as an addition to uranium dioxide.  
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 comply with all federal, state, and local regulations pertaining to possessing, shipping, processing, or using this material.  
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 covers silver-indium-cadmium alloy for use as a control material in light-water nuclear reactors. The use of this material in applications is excluded where material strength of this alloy is a prime requisite. Also, this material must be protected from the primary water by a corrosion and wear resistant cladding. The identity of each lot by melt number shall be maintained at all stages of manufacture. Parts produced to this specification shall be made from billets by hot working and cold finishing to size. The cold-finished parts shall be produced to the finish condition and dimensions as specified. The surface of the cold-finished part shall be free of oxides, grease, oil, residual lubricants, inclusions, and other extraneous materials. Surface defects such as folds, cracks, seams, slivers, and blisters shall be cause for rejection.
SCOPE
1.1 This specification covers silver-indium-cadmium alloy for use as a control material in light-water nuclear reactors.  
1.2 The scope of this specification excludes the use of this material in applications where material strength of this alloy is a prime requisite. Also, this material must be protected from the primary water by a corrosion and wear resistant cladding.  
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
3.1 Aluminum oxide pellets are used in a reactor core as filler or spacers within fuel, burnable poison, or control rods. In order to be suitable for this purpose, the material must meet certain criteria for impurity content. These test methods are designed to show whether or not a given material meets the specifications for these items as described in Specification C785.  
3.1.1 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.  
3.2 Aluminum oxide-boron carbide composite pellets are used in a reactor core as a component in neutron absorber rods. In order to be suitable for this purpose, the material must meet certain criteria for boron content, isotopic composition, and impurity content as described in Specification C784.  
3.2.1 The material is assayed for boron to determine whether the boron content is as specified by the purchaser.  
3.2.2 Determination of the isotopic content of the boron is made to establish whether the 10B concentration is in compliance with the purchaser's specifications.  
3.2.3 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.
SCOPE
1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade aluminum oxide and aluminum oxide-boron carbide composite pellets to determine compliance with specifications.  
1.2 The analytical procedures appear in the following order:    
Sections  
Boron by Titrimetry and ICP OES  
7 to 16  
Separation of Boron for Mass Spectrometry  
17 to 22  
Isotopic Composition by Mass Spectrometry  
23 to 26  
Separation of Halides by Pyrohydrolysis  
27 to 30  
Chloride and Fluoride by Ion-Selective Electrode  
31 to 33  
Chloride, Bromide, and Iodide by Amperometric Microtitrimetry  
34 to 36  
Trace Elements by Emission Spectroscopy  
37 to 49  
Keywords  
50
1.3 The values stated in SI units are to be regarded as the 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. (For specific precautionary statements, see Section 5.)

SIGNIFICANCE AND USE
Boron carbide is used as a control material in nuclear reactors. In order to be suitable for this purpose, the material must meet certain criteria for assay, isotopic composition, and impurity content. These methods are designed to show whether or not a given material meets the specifications for these items as described in Specifications C750 and C751.
An assay is performed to determine whether the material has the specified boron content.
Determination of the isotopic content of the boron is made to establish whether the content is in compliance with the purchaser’s specifications.
Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.
SCOPE
1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade boron carbide powder and pellets to determine compliance with specifications.
1.2 The analytical procedures appear in the following order:
Sections Total Carbon by Combustion in an Inductive Furnace and Infrared Measurement 7-16 Total Boron by Titrimetry and ICP OES17-27 Isotopic Composition by Mass Spectrometry28-32 Pyrohydrolysis33-40 Chloride by Constant-Current Coulometry41-49 Chloride and Fluoride by Ion-Selective Electrode50-58 Water by Constant-Voltage Coulometry and Weight Loss on Drying59-62 Metallic Impurities63 and 64 Soluble Boron by Titrimetry and ICP OES65-79 Free Carbon by a Coulometric Method80-89

SCOPE
1.1 This specification applies to boron carbide pellets for use as a control material in nuclear reactors.
1.2 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 composite pellets composed of mixtures of nuclear-grade aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods. Specimens shall be sampled and tested as appropriate, and shall adhere accordingly to required chemical compositions, physical dimensions, density, boron carbide homogeneity, mechanical properties, visual appearance, end and circumferential chips, cracks, and fissures and other defects.
SCOPE
1.1 This specification applies to pellets composed of mixtures of aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods.
1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

SIGNIFICANCE AND USE
Boron carbide is used as a control material in nuclear reactors. In order to be suitable for this purpose, the material must meet certain criteria for assay, isotopic composition, and impurity content. These methods are designed to show whether or not a given material meets the specifications for these items as described in Specifications C750 and C751.
An assay is performed to determine whether the material has the specified boron content.
Determination of the isotopic content of the boron is made to establish whether the content is in compliance with the purchaser’s specifications.
Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.
SCOPE
1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade boron carbide powder and pellets to determine compliance with specifications.
1.2 The analytical procedures appear in the following order:
Sections Total Carbon by Combustion in an Inductive Furnace and Infrared Measurement 7-16 Total Boron by Titrimetry and ICP OES17-27 Isotopic Composition by Mass Spectrometry28-32 Pyrohydrolysis33-40 Chloride by Constant-Current Coulometry41-49 Chloride and Fluoride by Ion-Selective Electrode50-58 Water by Constant-Voltage Coulometry and Weight Loss on Drying59-62 Metallic Impurities63 and 64 Soluble Boron by Titrimetry and ICP OES65-79 Free Carbon by a Coulometric Method80-89  
7.1 This method covers the determination of total carbon in nuclear-grade boron carbide in either powder or pellet form.  
17.1 This method covers the determination of total boron in samples of boron carbide powder and pellets by titrimetry and ICP OES. The recommended amount of boron for each titration is 100 ± 10 mg.  
28.1 This method covers the determination of the isotopic composition of boron in nuclear-grade boron carbide, in powder and pellet form, containing natural to highly enriched boron.  
33.1 This method covers the separation of up to 100 μg of halides per gram of boron carbide. The separated halides are measured using other methods found in this standard. It also covers the sample preparation for the determination of isotopic composition by ICP MS.  
41.1 This method covers the measurement of chloride after separation from boron carbide by pyrohydrolysis. The lower limit of the method is about 2 μg of chloride per titration.  
50.1 This method covers the measurement of chloride and fluoride after separation from boron carbide by pyrohydrolysis. The limit of detection for chloride and fluoride in the boron carbide sample is 3 mg/kg and 2 mg/kg, respectively.  
60.1 This method covers the determination of water in boron carbide in either powder or pellet form. The lower limit of the method is 5 μg of water. The lower limit of the weight loss on drying method is 20 mg/kg for a sample mass of 5 g.  
65.1 This method covers the determination of soluble boron in boron carbide. Soluble boron is defined as that boron dissolved under the conditions of the test.  
80.1 This method covers the determination of free carbon (also called soluble carbon) in boron carbide powders and shaped or sintered bodies of boron carbide after crushing. This method is applicable to mass fractions of free carbon of 0.01 % to 10 %.

ABSTRACT
This specification provides the chemical and physical properties and requirements for nuclear-grade aluminum oxide powder intended for fabrication into shapes for nuclear applications. The materials shall conform to physical requirements as to particle size distribution, and specific surface area, and chemical requirements as to loss-on-ignition, and total and elemental concentrations of all impurities. Impurities may include silicaon, iron-chromium-nickel, magnesium, sodium, calcium, hafnium, fluorine, fluorine-chlorine-iodine-bromine, gadolinium, samarium, europium, and dysprosium.
SCOPE
1.1 This specification provides the chemical and physical requirements for nuclear-grade aluminum oxide powder intended for fabrication into shapes for nuclear applications. Two specific uses for which this powder is intended are Al2O3 pellets and Al2O 3 − B4C composite pellets for use as thermal insulator or burnable neutron absorbers, respectively.
1.2 The material described herein shall be particulate in nature.

ABSTRACT
This specification defines essential criteria for all material combinations in boron-based neutron-absorbing material systems used for nuclear spent fuel storage racks in nuclear light water reactors, spent-fuel assemblies, or disassembled components. The boron-based neutron absorbing materials normally consist of metallic boron or a boron-containing boron compound supported by a matrix of aluminum, steel, or other materials. Material systems covered in this specification should always be capable of maintaining a B10 areal density that can support the required subcriticality depending on the design specification for service life.
SCOPE
1.1 This specification defines criteria for boron-based neutron absorbing material systems used in racks in a pool environment for storage of nuclear light water reactor (LWR) spent-fuel assemblies or disassembled components to maintain sub-criticality in the storage rack system.
1.2 Boron-based neutron absorbing material systems normally consist of metallic boron or a chemical compound containing boron (for example, boron carbide, B4C) supported by a matrix of aluminum, steel, or other materials.
1.3 In a boron-based absorber, neutron absorption occurs primarily by the boron-10 isotope that is present in natural boron to the extent of 18.3 ± 0.2 % by weight (depending upon the geological origin of the boron). Boron, enriched in boron-10 could also be used.  
1.4 The materials systems described herein shall be functional – that is always be capable to maintain a B10 areal density such that subcriticality Keff 0.95 or Keff 0.98 or Keff  1.0 depending on the design specification for the service life in the operating environment of a nuclear spent fuel pool.
1.5 A number of acceptable boron-based absorbing materials combinations are currently available while others are being developed for use in the future. This specification defines criteria essential and applicable to all materials combinations and identifies parameters a buyer should specify to satisfy a unique or particular requirement.
1.6 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to conform to all applicable international, national, and local regulations.

ABSTRACT
This specification covers silver-indium-cadmium alloy for use as a control material in light-water nuclear reactors. The use of this material in applications is excluded where material strength of this alloy is a prime requisite. Also, this material must be protected from the primary water by a corrosion and wear resistant cladding. The identity of each lot by melt number shall be maintained at all stages of manufacture. Parts produced to this specification shall be made from billets by hot working and cold finishing to size. The cold-finished parts shall be produced to the finish condition and dimensions as specified. The surface of the cold-finished part shall be free of oxides, grease, oil, residual lubricants, inclusions, and other extraneous materials. Surface defects such as folds, cracks, seams, slivers, and blisters shall be cause for rejection.
SCOPE
1.1 This specification covers silver-indium-cadmium alloy for use as a control material in light-water nuclear reactors.
1.2 The scope of this specification excludes the use of this material in applications where material strength of this alloy is a prime requisite. Also, this material must be protected from the primary water by a corrosion and wear resistant cladding.
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 pellets of stabilized zirconium oxide used in nuclear reactors. The chemical composition requirements such as the stabilizing additive (calcium oxide or yttrium oxide), analytical chemistry methods, impurity concentration (including hafnium, boron, gadolinium, samarium, europium, dysprosium, cobalt, silicon, iron, calcium, magnesium, aluminum, titanium, thorium, fluorine, chlorine, bromine, iodine, and hydrogen), and moisture concentration are prescribed. The nuclear grade pellets shall conform to the specified physical requirements which includes the following: physical dimensions, density, mechanical properties and test methods such as compressive test and thermal cycling test, and visual appearance such as end chips, circumferential chips, cracks, and fissures. The requirements for cleanliness before and after sampling and packaging are given.
SCOPE
1.1 This specification applies to pellets of stabilized zirconium oxide used in nuclear reactors.
1.2 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 defines the chemical and physical requirements for boron carbide powder intended for a variety of nuclear applications. The powder shall be classified as: Type 1; Type 2; and Type 3. The material shall conform to the chemical composition requirements prescribed. Quality control tests, acceptance tests, referee tests, and retention of archive samples by the seller shall be performed to conform to the specified requirements.
SCOPE
1.1 This specification defines the chemical and physical requirements for boron carbide powder intended for a variety of nuclear applications. Because each application has a different need for impurity and boron requirements, three different chemical compositions of powder are specified. In using this specification, it is necessary to dictate which type of powder is intended to be used. In general, the intended applications for the various powder types are as follows:
1.1.1 Type 1—For use as particulate material in nuclear reactor core applications.
1.1.2 Type 2—Powder that will be further processed into a fabricated shape for use in a nuclear reactor core or used in non-core applications when the powder directly or indirectly may cause adverse effects on structural components, such as halide stress corrosion of stainless steel.
1.1.3 Type 3—Powder that will be used for non-core applications or special in-core applications.  
1.2 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 covers the properties and requirements for pellets of stabilized cubic hafnium oxide used in nuclear reactors. Hafnium oxide should consist of a stabilizing agent, the recommended of which is yttrium oxide, though others such as calcium oxide and magnesium oxide may also be used as agreed upon by the buyer and seller. The material shall meet specified values of the following requirements: physical dimensions; density; mechanical properties; phase stabilization; impurity concentration limits; moisture concentration limit; visual appearance; end and circumferential chips; cracks; and fissures and other defects.
SCOPE
1.1 This specification applies to pellets of stabilized cubic hafnium oxide used in nuclear reactors.
1.2 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 defines the physical and chemical requirements for zirconium oxide powder intended for fabrication into shapes, either entirely or partially of zirconia, for use in a nuclear reactor core.
1.2 The material described herein shall be particulate in nature.
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

SCOPE
1.1 This specification applies to pellets of aluminum oxide that may be ultimately used in a reactor core, for example, as filler or spacers within fuel, burnable poison, or control rods. In order to distinguish between the subject pellets and “burnable poison” pellets, it is established that the subject pellets are not intended to be used as neutron-absorbing material.
1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.