This document provides guidance in the preparation, verification, and validation of group-averaged neutron and gamma-ray cross sections for the energy range and materials of importance in radiation protection and shielding calculations for nuclear reactors, see also Annex A.
 This edition is based on ANSI/ANS-6.1.2-2013.
Status: PublishedPublication date: 2022-05
Edition: 1Number of pages: 10
Technical Committee: ISO/TC 85/SC 6 Reactor technology
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