ASTM E 910 : 2018
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
Hardcopy , PDF
10-06-2024
English
01-02-2018
Committee |
E 10
|
DocumentType |
Test Method
|
Pages |
12
|
PublisherName |
American Society for Testing and Materials
|
Status |
Superseded
|
SupersededBy | |
Supersedes |
1.1This test method describes the concept and use of helium accumulation for neutron fluence dosimetry for reactor vessel surveillance. Although this test method is directed toward applications in vessel surveillance, the concepts and techniques are equally applicable to the general field of neutron dosimetry. The various applications of this test method for reactor vessel surveillance are as follows:
1.1.1Helium accumulation fluence monitor (HAFM) capsules,
1.1.2Unencapsulated, or cadmium or gadolinium covered, radiometric monitors (RM) and HAFM wires for helium analysis,
1.1.3Charpy test block samples for helium accumulation, and
1.1.4Reactor vessel (RV) wall samples for helium accumulation.
1.2This 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.
1.3This 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.
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ASTM E 482 : 2016 | Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance |
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ASTM E 2005 : 1999 | Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields |
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ASTM E 900 : 2015 : EDT 2 | Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials |
ASTM E 944 : 1996 | Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA) |
ASTM E 2005 : 2005 : EDT 1 | Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields |
ASTM E 261 : 2016 | Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques |
ASTM E 706 : 2001 | Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0) |
ASTM E 170 : 2023 | Standard Terminology Relating to Radiation Measurements and Dosimetry |
ASTM E 853 : 2023 | Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results |
ASTM E 1018 : 2009 | Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB) |
ASTM C 859 : 2022 | Standard Terminology Relating to Nuclear Materials |
ASTM C 859 : 2022 : REV A | Standard Terminology Relating to Nuclear Materials |
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ASTM E 1005 : 2021 | Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance |
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ASTM E 1018 : 2001 | Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB) |
ASTM E 1005 : 1997 | Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA) |
ASTM E 1005 : 2003 : EDT 1 | Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA) |
ASTM E 900 : 2021 | Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials |
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ASTM E 261 : 2016 : R2021 | Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques |
ASTM E 1005 : 2016 | Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance |
ASTM E 1018 : 1995 | Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB) |
ASTM E 482 : 2022 | Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance |
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