ASTM E2006 - 16 - Standard Guide for Benchmark Testing of Light Water Reactor Calculations

ASTM E2006 - 16

Standard Guide for Benchmark Testing of Light Water Reactor Calculations

Status : Current   Published : June 2016

Format
PDF

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HARDCOPY



1.1 This 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.

1.2  This 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.




Standard NumberASTM E2006 - 16
TitleStandard Guide for Benchmark Testing of Light Water Reactor Calculations
StatusCurrent
Publication Date01 June 2016
Normative References(Required to achieve compliance to this standard)No other standards are normatively referenced
Informative References(Provided for Information)No other standards are informatively referenced
Descriptors Benchmark testing, Calculational methods, Least-square adjustment, Neutron transport calculations, Nuclear data, Reactor pressure vessel, Uncertainty estimates
ICS27.120.10
PublisherASTM
FormatA4
DeliveryYes
Pages7
File Size122 KB
Price£40.00


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