ASTM E1214-87(2000)
(Guide)Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E706(IIIE)
Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E706(IIIE)
SCOPE
1.1 This guide describes the application of melt wire temperature monitors and their use for reactor vessel surveillance of light-water power reactors as called for in Practice E185.
1.2 The purpose of this guide is to recommend the selection and use of the common melt wire technique where the correspondence between melting temperature and composition of different alloys is used as a passive temperature monitor. Guidelines are provided for the selection and calibration of monitor materials; design, fabrication, and assembly of monitor and container; post-irradiation examinations; interpretation of the results; and estimation of uncertainties.
1.3 This standard may involve hazardous materials, operations, and equipment. This standard does not purport to address all of the safety problems 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. (See Note.)
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Designation:E1214–87(Reapproved 2000)
Standard Guide for
Use of Melt Wire Temperature Monitors for Reactor Vessel
Surveillance, E 706(IIIE)
This standard is issued under the fixed designation E 1214; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
1. Scope ing of surveillance specimens beyond the expected tempera-
ture. Since overheating causes a reduction in the amount of
1.1 This guide describes the application of melt wire tem-
radiation damage to the surveillance specimens, this overheat-
perature monitors and their use for reactor vessel surveillance
ing could result in a change in the measured properties of the
of light-water power reactors as called for in Practice E 185.
surveillance specimens that would lead to an unconservative
1.2 The purpose of this guide is to recommend the selection
prediction of damage to the reactor vessel material.
and use of the common melt wire technique where the
3.2 The magnitude of the reduction of radiation damage
correspondence between melting temperature and composition
with overheating depends on the composition of the material
of different alloys is used as a passive temperature monitor.
andtimeattemperature;thereisnotyetanacceptedmethodfor
Guidelines are provided for the selection and calibration of
quantifying the effect. Because the evidence from melt wire
monitor materials; design, fabrication, and assembly of moni-
monitors gives no indication of the duration of overheating
tor and container; post-irradiation examinations; interpretation
above the expected temperature as indicated by melting of the
of the results; and estimation of uncertainties.
monitor, the significance of overheating events cannot be
1.3 This standard does not purport to address all of the
quantified on the basis of thermal monitors alone. Indication of
safety concerns, if any, associated with its use. It is the
an overtemperature does serve to alert the user of the data to
responsibility of the user of this standard to establish appro-
further evaluate the irradiation temperature exposure history of
priate safety and health practices and determine the applica-
the surveillance capsule.
bility of regulatory limitations prior to use. (See Note 1.)
3.3 This guide is IIIE of Master Matrix E 706 that relates
2. Referenced Documents
several standards used for irradiation surveillance of light
water reactor vessel materials. It is intended primarily to
2.1 ASTM Standards:
amplifytherequirementsofPracticeE 185.Itmayalsobeused
E 185 Practice for Conducting Surveillance Tests for Light-
,
2 3
in conjunction with Guide E 844.
Water Cooled Nuclear Power Reactor Vessels, (IF)
E 706 Master Matrix for Light-Water Reactor Pressure
4. Selection and Calibration of Monitor Materials
Vessel Surveillance Standards
4.1 Selection of Monitor Materials:
E 794 Test Method for Melting and Crystallization Tem-
4 4.1.1 Materials selected for thermal monitors shall possess
perature by Thermal Analysis
unique melting temperatures. Since composition, and particu-
E 844 Guide for Sensor Set Design and Irradiation for
,
2 3 larly the presence of impurities, strongly influence melting
Reactor Surveillance, (IIC)
temperature, the fabricated monitor materials shall consist of
3. Significance and Use either metals of purity 99.9 % or greater or eutectic alloys such
that the measured melting temperature is within6 3°C of the
3.1 Temperature monitors are used in surveillance capsules,
recognized melting temperature. Transmutation-induced
in accordance with Practice E 185, to verify the estimated
changes of the monitor materials suggested in 4.1.2 are not
valuesofirradiationtemperatureofthesurveillancespecimens.
considered significant for fluences to 1 3 10 n/cm2 (E > 1
Temperature monitors are needed to give evidence of overheat-
MeV) relative to the goal of these thermal monitors in flagging
deviations from expected temperatures.
This guide is under the jurisdiction of ASTM Committee E-10 on Nuclear
4.1.2 The monitor materials in Table 1 provide temperature
Technology and Applications and is the direct responsibility of Subcommittee
indicationsintherangeof266to327°C.Othermetalsoralloys
E10.02 on Behavior and Use of Metallic Materials in Nuclear Systems.
may be selected for the temperatures of interest provided the
Current edition approved Nov. 27, 1987. Published January 1988.
monitor materials meet the technical requirements of this
The reference Master Matrix designation in parentheses refers to Section 5, as
well as Figs. 1 and 2 of Matrix E 706.
guide.
Annual Book of ASTM Standards, Vol 12.02.
Annual Book of ASTM Standards, Vol 14.02.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
E1214
TABLE 1 Monitor Material Melting Temperature
capsule must be maintained. Provision for means of verifica-
Monitor Material, Weight % Melting Temperature, °C tion shall be by design.
Cd–17.4 Zn 266
6. Post-Irradiation Examination
Au–20.0 Sn 280
Pb–5.0 Ag–5.0 Sn 292
6.1 Following irradiation, the temperature monitors shall be
Pb–2.5 Ag 304
examined for evidence of melting to establish the maximum
Pb–1.5 Ag–1.0 Sn 309
Pb–1.75 Ag–0.75 Sn 310 exposure temperature of the encapsulated surveillance speci-
Cd–1.2 Cu 314
mens. Precautions should be taken while recovering the moni-
Cd 321
tors from the surveillance capsule and during subsequent
Pb 327
examination.
6.1.1 The monitor design and method of encapsulation shall
be considered in the recovery procedure to ensure that the
4.1.3 The chosen monitor materials shall be carefully evalu-
monitors are not damaged and that the original identity of
ated for radiological health hazards.
individual monitors and their location is maintained.
NOTE 1—It is beyond the scope of this guide to provide safety and
6.1.2 Recovery and examination of the monitors should be
health criteria, and the user is cautioned to seek further guidance.
performed remotely or with sufficient shielding to protect the
4.2 Calibration of Monitor Materials— Each lot of monitor
operator from unnecessary radiation exposure.
materials shall be calibrated by melting tests to establish the
6.2 Evaluation of the temperature monitors after service for
actual melting temperatures. The melting temperature tests
evidence of melting should be performed using suitable equip-
shallbeconductedinaccordancewithTestMethodE 794.Ifan
ment that is dependent on the design of the monitor container
alternate method of calibration is used, the procedure and
and the examination facility. When visual inspection of the
equipment must be described, the resultant mean values and
monitors is possible, such as with periscopes, each monitor
uncertainties
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