本文件为核反应堆辐射防护和屏蔽计算[1]中重要的能量范围和材料的群平均中子和γ射线截面的制备、验证和验证提供了指导，另见附件A. ？ [1] 本版本基于ANSI/ANS-6.1.2-2013。

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[1], see also Annex？A. ？ [1] This edition is based on ANSI/ANS-6.1.2-2013^[1].