ASTM E 482 : 2016
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by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 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
Hardcopy , PDF
23-08-2022
English
10-08-2016
Committee |
E 10
|
DocumentType |
Guide
|
Pages |
5
|
PublisherName |
American Society for Testing and Materials
|
Status |
Superseded
|
SupersededBy | |
Supersedes |
1.1Need for Neutronics Calculations—An accurate calculation of the neutron fluence and fluence rate at several locations is essential for the analysis of integral dosimetry measurements and for predicting irradiation damage exposure parameter values in the pressure vessel. Exposure parameter values may be obtained directly from calculations or indirectly from calculations that are adjusted with dosimetry measurements; Guide E944 and Practice E853 define appropriate computational procedures.
1.2Methodology—Neutronics calculations for application to reactor vessel surveillance encompass three essential areas: (1) validation of methods by comparison of calculations with dosimetry measurements in a benchmark experiment, (2) determination of the neutron source distribution in the reactor core, and (3) calculation of neutron fluence rate at the surveillance position and in the pressure vessel.
1.3This 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 requirements prior to use.
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ASTM E 1854 : 2019 | Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts |
ASTM E 900 : 2021 | Standard Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials |
ASTM E 2005 : 2021 | Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields |
ASTM E 1035 : 2018 | Standard Practice for Determining Neutron Exposures for Nuclear Reactor<brk/> Vessel Support Structures |
ASTM E 1006 : 2021 | Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments |
ASTM E 706 : 2016 | Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards |
ASTM E 2232 : 2021 | Standard Guide for Selection and Use of Mathematical Methods for Calculating Absorbed Dose in Radiation Processing Applications |
ASTM E 853 : 2018 | Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results |
ASTM E 1005 : 2021 | Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance |
ASTM E 185 : 2021 | Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels |
ASTM E 2956 : 2021 | Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels |
ASTM E 706 : 2016 | Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards |
ASTM E 2006 : 2022 | Standard Guide for Benchmark Testing of Light Water Reactor Calculations |
ASTM E 1018 : 2020 | Standard Guide for Application of ASTM Evaluated Cross Section Data File |
ASTM E 1018 : 2009 : R2013 : EDT 1 | Standard Guide for Application of ASTM Evaluated Cross Section Data File |
ASTM E 944 : 1996 | Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA) |
ASTM E 2006 : 1999 | Standard Guide for Benchmark Testing of Light Water Reactor Calculations |
ASTM E 706 : 2001 | Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0) |
ASTM E 2006 : 2005 | Standard Guide for Benchmark Testing of Light Water Reactor Calculations |
ASTM E 1018 : 2009 | Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB) |
ASTM E 1018 : 2009 : R2013 | Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB) |
ASTM E 1018 : 2001 | Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB) |
ASTM E 2006 : 2016 | Standard Guide for Benchmark Testing of Light Water Reactor Calculations |
ASTM E 2006 : 2010 | Standard Guide for Benchmark Testing of Light Water Reactor Calculations |
ASTM E 1018 : 2020 : EDT 1 | Standard Guide for Application of ASTM Evaluated Cross Section Data File |
ASTM E 1018 : 1995 | Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB) |
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