ASTM E 1214 : 2011 : R2018
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance
Hardcopy , PDF
14-01-2023
English
11-01-2018
CONTAINED IN VOL. 12.02, 2018 Specifies 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 and E 2215.
Committee |
E 10
|
DocumentType |
Guide
|
Pages |
3
|
ProductNote |
Reconfirmed 2018
|
PublisherName |
American Society for Testing and Materials
|
Status |
Superseded
|
SupersededBy | |
Supersedes |
1.1This 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.
1.2The 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.
1.3The 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.
1.4This 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. (See Note 1.)
1.5This 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.
ASTM E 853 : 2018 | Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results |
ASTM E 2215 : 2019 | Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels |
ASTM E 1005 : 2016 | Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance |
ASTM E 185 : 2016 | Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels |
ASTM E 1005 : 2021 | Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance |
ASTM E 185 : 1998 | Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF) |
ASTM E 706 : 2016 | Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards |
ASTM E 2215 : 2015 | Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels |
ASTM E 900 : 2015 : EDT 2 | Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials |
ASTM E 2215 : 2002 | Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels |
ASTM E 2215 : 2010 | Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels |
ASTM E 706 : 2001 | Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0) |
ASTM E 2215 : 2016 | Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels |
ASTM E 2215 : 2019 | Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels |
ASTM E 900 : 2021 | Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials |
ASTM E 185 : 2021 | Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels |
ASTM E 185 : 2016 : REDLINE | Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels |
ASTM E 2215 : 2018 | Standard Practice for Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels |
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