ASTM E1214-11e1

Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance

SIGNIFICANCE AND USE
3.1 Temperature monitors are used in surveillance capsules in accordance with Practice E2215 to estimate the maximum 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 temperature 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 This guide is included in Master Matrix E706 that relates several standards used for irradiation surveillance of light water reactor 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 E2215 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 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 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.)  
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.

General Information

• Status: Historical
• Publication Date: 30-Jun-2011
• ICS: 27.120.20 - Nuclear power plants. Safety
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.02 - Behavior and Use of Nuclear Structural Materials

Relations

• Replaces: ASTM E1214-11 - Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance, E 706 (IIIE)
• Effective Date: 01-Jul-2011
• Referred By: ASTM E2215-19 - Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Jul-2011
• Referred By: ASTM E853-23 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
• Effective Date: 01-Jul-2011
• Referred By: ASTM E185-21 - Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
• Effective Date: 01-Jul-2011
• Referred By: ASTM E1005-21 - Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
• Effective Date: 01-Jul-2011

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
´1
Designation: E1214 − 11
Standard Guide for
Use of Melt Wire Temperature Monitors for Reactor Vessel
1
Surveillance
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
ε NOTE—The title of this guide and the Referenced Documents were updated editorially in May 2017.
1. Scope 2. Referenced Documents
2
1.1 This guide describes the application of melt wire tem- 2.1 ASTM Standards:
perature monitors and their use for reactor vessel surveillance E185Practice for Design of Surveillance Programs for
of light-water power reactors as called for in Practices E185 Light-Water Moderated Nuclear Power Reactor Vessels
and E2215. E706MasterMatrixforLight-WaterReactorPressureVessel
Surveillance Standards
1.2 Thepurposeofthisguideistorecommendtheselection
E794TestMethodforMeltingAndCrystallizationTempera-
and use of the common melt wire technique where the
tures By Thermal Analysis
correspondence between melting temperature and composition
E900Guide for Predicting Radiation-Induced Transition
of different alloys is used as a passive temperature monitor.
Temperature Shift in Reactor Vessel Materials
Guidelines are provided for the selection and calibration of
E2215Practice for Evaluation of Surveillance Capsules
monitor materials; design, fabrication, and assembly of moni-
from Light-Water Moderated Nuclear Power ReactorVes-
tor and container; post-irradiation examinations; interpretation
sels
of the results; and estimation of uncertainties.
3. Significance and Use
1.3 The values stated in SI units are to be regarded as
standard. The values given in parentheses are mathematical
3.1 Temperature monitors are used in surveillance capsules
conversions to inch-pound units that are provided for informa-
in accordance with Practice E2215 to estimate the maximum
tion only and are not considered standard.
value of the surveillance specimen irradiation temperature.
Temperaturemonitorsareneededtogiveevidenceofoverheat-
1.4 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the ing of surveillance specimens beyond the expected tempera-
ture. Because overheating causes a reduction in the amount of
responsibility of the user of this standard to establish appro-
priate safety and health practices and determine the applica- neutron radiation damage to the surveillance specimens, this
overheatingcouldresultinachangeinthemeasuredproperties
bility of regulatory limitations prior to use. (See Note 1.)
1.5 This international standard was developed in accor- of the surveillance specimens that would lead to an unconser-
vative prediction of damage to the reactor vessel material.
dance with internationally recognized principles on standard-
ization established in the Decision on Principles for the
3.2 The magnitude of the reduction of radiation damage
Development of International Standards, Guides and Recom-
with overheating depends on the composition of the material
mendations issued by the World Trade Organization Technical
and time at temperature. Guide E900 provides an accepted
Barriers to Trade (TBT) Committee.
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
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
2
E10.02 on Behavior and Use of Nuclear Structural Materials. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved July 1, 2011. Published September 2011. Originally contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
approved in 1987. Last previous edition approved in 2006 as E1214–06. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/E1214-11E01. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
´1
E1214 − 11
indicated by melting of the monitor, the significance of 5. Design, Fabrication, and Assembly of Monitor and
overheating events cannot be quantified on the basis of Container
temperature monitors alone. Indication of overheating does
5.1 The design of the monitor and its container shall ensure
serve to alert the user of the data to further evaluate the
thatthemaximumtemperatureofthesurveillancespecimensis
irradiation temperature exposure history
...

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.
´1
Designation: E1214 − 11 E1214 − 11
Standard Guide for
Use of Melt Wire Temperature Monitors for Reactor Vessel
1
Surveillance, E 706 (IIIE)Surveillance
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
ε NOTE—The title of this guide and the Referenced Documents were updated editorially in May 2017.
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 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.)
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.
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
E794 Test Method for Melting And Crystallization Temperatures By Thermal Analysis
E900 Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
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 estimate the maximum 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
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applicationsand is the direct responsibility of Subcommittee E10.02 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/E1214-11.10.1520/E1214-11E01.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
´1
E1214 − 11
monitor, the significance of overheating events cannot be quantifie
...