ASTM E1214-11
(Guide)Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E 706 (IIIE)
Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E 706 (IIIE)
SIGNIFICANCE AND USE
Temperature monitors are used in surveillance capsules in accordance with Practice E 2215 to verify the estimated value of the surveillance specimen irradiation temperature. Temperature monitors are needed to give evidence of overheating of surveillance specimens beyond the expected temperature. Because overheating causes a reduction in the amount of neutron radiation damage to the surveillance specimens, this overheating could result in a change in the measured properties of the surveillance specimens that would lead to an unconservative prediction of damage to the reactor vessel material.
The magnitude of the reduction of radiation damage with overheating depends on the composition of the material and time at temperature. Guide E 900 provides an accepted method for quantifying the temperature effect. Because the evidence from melt wire monitors gives no indication of the duration of overheating above the expected temperature as indicated by melting of the monitor, the significance of overheating events cannot be quantified on the basis of thermal monitors alone. Indication of overheating does serve to alert the user of the data to further evaluate the irradiation temperature exposure history of the surveillance capsule.
This guide is IIIE of Master Matrix E 706 that relates several standards used for irradiation surveillance of light water reactor vessel materials. It is intended primarily to amplify the requirements of Practice E 185 in the design of temperature monitors for the surveillance program. It may also be used in conjunction with Practice E 2215 to evaluate the post-irradiation test measurements..
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 E 185.
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 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. (See Note 1.)
General Information
Relations
Buy Standard
Standards Content (Sample)
NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: E1214 − 11
Standard Guide for
Use of Melt Wire Temperature Monitors for Reactor Vessel
1
Surveillance, E 706 (IIIE)
This standard is issued under the fixed designation E1214; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope E794TestMethodforMeltingAndCrystallizationTempera-
tures By Thermal Analysis
1.1 This guide describes the application of melt wire tem-
E900Guide for Predicting Radiation-Induced Transition
perature monitors and their use for reactor vessel surveillance
Temperature Shift in ReactorVessel Materials, E706 (IIF)
of light-water power reactors as called for in Practices E185
E2215Practice for Evaluation of Surveillance Capsules
and E2215.
from Light-Water Moderated Nuclear Power ReactorVes-
1.2 Thepurposeofthisguideistorecommendtheselection
sels
and use of the common melt wire technique where the
correspondence between melting temperature and composition
3. Significance and Use
of different alloys is used as a passive temperature monitor.
3.1 Temperature monitors are used in surveillance capsules
Guidelines are provided for the selection and calibration of
in accordance with Practice E2215 to estimate the maximum
monitor materials; design, fabrication, and assembly of moni-
value of the surveillance specimen irradiation temperature.
tor and container; post-irradiation examinations; interpretation
Temperaturemonitorsareneededtogiveevidenceofoverheat-
of the results; and estimation of uncertainties.
ing of surveillance specimens beyond the expected tempera-
1.3 The values stated in SI units are to be regarded as
ture. Because overheating causes a reduction in the amount of
standard. The values given in parentheses are mathematical
neutron radiation damage to the surveillance specimens, this
conversions to inch-pound units that are provided for informa-
overheatingcouldresultinachangeinthemeasuredproperties
tion only and are not considered standard.
of the surveillance specimens that would lead to an unconser-
1.4 This standard does not purport to address all of the
vative prediction of damage to the reactor vessel material.
safety concerns, if any, associated with its use. It is the
3.2 The magnitude of the reduction of radiation damage
responsibility of the user of this standard to establish appro-
with overheating depends on the composition of the material
priate safety and health practices and determine the applica-
and time at temperature. Guide E900 provides an accepted
bility of regulatory limitations prior to use. (See Note 1.)
method for quantifying the temperature effect. Because the
evidence from melt wire monitors gives no indication of the
2. Referenced Documents
duration of overheating above the expected temperature as
2,3
2.1 ASTM Standards:
indicated by melting of the monitor, the significance of
E185Practice for Design of Surveillance Programs for
overheating events cannot be quantified on the basis of
Light-Water Moderated Nuclear Power Reactor Vessels
temperature monitors alone. Indication of overheating does
E706MasterMatrixforLight-WaterReactorPressureVessel
serve to alert the user of the data to further evaluate the
4
Surveillance Standards, E 706(0) (Withdrawn 2011)
irradiation temperature exposure history of the surveillance
capsule.
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
3.3 This guide is IIIE of Master Matrix E706 that relates
Technology and Applicationsand is the direct responsibility of Subcommittee
E10.02 on Behavior and Use of Nuclear Structural Materials.
several standards used for irradiation surveillance of light
Current edition approved July 1, 2011. Published September 2011. Originally
water reactor vessel materials. It is intended primarily to
approved in 1987. Last previous edition approved in 2006 as E1214–06. DOI:
amplify the requirements of Practice E185 in the design of
10.1520/E1214-11.
2
The reference Master Matrix designation in parentheses refers to Section 5, as temperaturemonitorsforthesurveillanceprogram.Itmayalso
well as Figs. 1 and 2 of Matrix E706.
be used in conjunction with Practice E2215 to evaluate the
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
post-irradiation test measurements.
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website.
4. Selection and Calibration of Monitor Materials
4
The last approved version of this historical standard is referenced on
www.astm.org. 4.1 Selection of Monitor Materials:
Copyright © ASTM International, 100
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation:E1214–06 Designation:E1214–11
Standard Guide for
Use of Melt Wire Temperature Monitors for Reactor Vessel
1
Surveillance, E 706(IIIE)
This standard is issued under the fixed designation E1214; 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 (´) indicates an editorial change since the last revision or reapproval.
1. 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 Practices E185 and E2215.
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
1.3 The values stated in SI units are to be regarded as standard. The values given in parentheses are mathematical conversions
to inch-pound units that are provided for information only and are not considered 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. (See Note 1.)
2. Referenced Documents
2
2.1 ASTM Standards:
E185 Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E 706(0)
E794 Test Method for Melting And Crystallization Temperatures By Thermal Analysis
E900 Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF)
E2215 Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
3. Significance and Use
3.1 Temperature monitors are used in surveillance capsules in accordance with Practice E2215 to verifyestimate the
estimatedmaximum value of the surveillance specimen irradiation temperature. Temperature monitors are needed to give evidence
of overheating of surveillance specimens beyond the expected temperature. Because overheating causes a reduction in the amount
of neutron radiation damage to the surveillance specimens, this overheating could result in a change in the measured properties
of the surveillance specimens that would lead to an unconservative prediction of damage to the reactor vessel material.
3.2 The magnitude of the reduction of radiation damage with overheating depends on the composition of the material and time
at temperature. Guide E900 provides an accepted method for quantifying the temperature effect. Because the evidence from melt
wire monitors gives no indication of the duration of overheating above the expected temperature as indicated by melting of the
monitor, the significance of overheating events cannot be quantified on the basis of thermaltemperature monitors alone. Indication
of overheating does serve to alert the user of the data to further evaluate the irradiation temperature exposure history of the
surveillance capsule.
3.3 ThisguideisIIIEofMasterMatrixE706thatrelatesseveralstandardsusedforirradiationsurveillanceoflightwaterreactor
vessel materials. It is intended primarily to amplify the requirements of Practice E185 in the design of temperature monitors for
the surveillance program. It may also be used in conjunction with Practice E2215to evaluate the post-irradiation test
measurements.
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.02 on
Behavior and Use of Metallic Materials in Nuclear Systems.
Current edition approved Jan. 1, 2006. Published February 2006. Originally approved in 1987. Last previous edition approved in 2000 as E1214–87(2000). DOI:
10.1520/E1214-06.on Behavior and Use of Nuclear Structural Materials.
Current edition approved July 1, 2011. Published September 2011. Originally approved in 1987. Last previous edition approved in 2006 as E1214–06. DOI:
10.1520/E1214-11.
2
The reference Maste
...
Questions, Comments and Discussion
Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.