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ASTM E 482 : 2016 : REDLINE

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by
superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
Available format(s)

PDF

Superseded date

23-08-2022

Language(s)

English

Published date

10-08-2016

Publisher

American Society for Testing and Materials

CONTAINED IN VOL. 12.02, 2016 Defines an accurate calculation of the neutron fluence and fluence rate at several locations essential for the analysis of integral dosimetry measurements and for predicting irradiation damage exposure parameter values in the pressure vessel.

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.

Committee
E 10
DocumentType
Redline
Pages
5
PublisherName
American Society for Testing and Materials
Status
Superseded
SupersededBy

ASTM E 1018 : 2009 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
ASTM E 2005 : 2010 : R2015 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
ASTM E 944 : 2013-01 GUIDE FOR APPLICATION OF NEUTRON SPECTRUM ADJUSTMENT METHODS IN REACTOR SURVEILLANCE
ASTM E 531 : 2013 : REDLINE Standard Practice for Surveillance Testing of High-Temperature Nuclear Component Materials (Withdrawn 2022)
ASTM E 1005 : 2016 : REDLINE Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
ASTM E 910 : 2018 : REDLINE Standard Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
ASTM E 2956 : 2014 Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels
ASTM E 2005:2010 Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
ASTM E 560 : 2001 Standard Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E706(IC) (Withdrawn 2009)
ASTM E 2232 : 2016 : REDLINE Standard Guide for Selection and Use of Mathematical Methods for Calculating Absorbed Dose in Radiation Processing Applications
ASTM E 1006 : 2013 : REDLINE 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 1018 : 2009 : R2013 : EDT 1 Standard Guide for Application of ASTM Evaluated Cross Section Data File
ASTM E 1854 : 2013 : REDLINE Standard Practice for Ensuring Test Consistency in Neutron-Induced Displacement Damage of Electronic Parts
ASTM E 185 : 2016 : REDLINE Standard Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
ASTM E 1018 : 2009 : R2013 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E706 (IIB)

ASTM E 706 : 2016 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
ASTM E 693 : 2017 : REDLINE Standard Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
ASTM E 2006 : 2016 : REDLINE Standard Guide for Benchmark Testing of Light Water Reactor Calculations
ASTM E 944 : 2013-01 GUIDE FOR APPLICATION OF NEUTRON SPECTRUM ADJUSTMENT METHODS IN REACTOR SURVEILLANCE

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