ASTM E 2006 : 2016 : REDLINE
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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 Benchmark Testing of Light Water Reactor Calculations
09-03-2022
English
01-06-2016
CONTAINED IN VOL. 12.02, 2016 Defines general approaches for benchmarking neutron transport calculations for pressure vessel surveillance programs in light water reactor systems.
Committee |
E 10
|
DocumentType |
Redline
|
Pages |
9
|
PublisherName |
American Society for Testing and Materials
|
Status |
Superseded
|
SupersededBy |
1.1This guide covers general approaches for benchmarking neutron transport calculations for pressure vessel surveillance programs in light water reactor systems. A companion guide (Guide E2005) covers use of benchmark fields for testing neutron transport calculations and cross sections in well controlled environments. This guide covers experimental benchmarking of neutron fluence calculations (or calculations of other exposure parameters such as dpa) in more complex geometries relevant to reactor pressure vessel surveillance. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to provide an indication of the accuracy of the calculational methods and nuclear data when applied to typical cases; and the use of plant specific measurements to indicate bias in individual plant calculations. Use of these two benchmark techniques will serve to limit plant-specific calculational uncertainty, and, when combined with analytical uncertainty estimates for the calculations, will provide uncertainty estimates for reactor fluences with a higher degree of confidence.
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 and health practices and determine the applicability of regulatory limitations prior to use.
ASTM E 482 : 2016 : REDLINE | Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance |
ASTM E 2005:2010 | Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields |
ASTM E 844 : 2009 : R2014 : EDT 1 | Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC) |
ASTM E 2005 : 2010 : R2015 | Standard Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields |
ISO 19226:2017 | Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals |
ASTM E 844 : 2009 : R2014 : EDT 2 | Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance |
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 2956 : 2014 | Standard Guide for Monitoring the Neutron Exposure of LWR Reactor Pressure Vessels |
BS ISO 19226:2017 | Nuclear energy. Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals |
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 |
17/30337935 DC : 0 | BS ISO 19226 - NUCLEAR ENERGY - DETERMINATION OF NEUTRON FLUENCE AND DISPLACEMENTS PER ATOM (DPA) IN REACTOR VESSEL AND INTERNALS |
ASTM E 844 : 2009 | Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC) |
ASTM E 706 : 2016 | Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards |
ASTM E 262 : 2017 : REDLINE | Standard Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques |
ASTM E 261 : 2016 : REDLINE | Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques |
ASTM E 944 : 2013-01 | GUIDE FOR APPLICATION OF NEUTRON SPECTRUM ADJUSTMENT METHODS IN REACTOR SURVEILLANCE |
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