Abstract
PreviewThis 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].
Buy this standard
en
| Format | Language | |
|---|---|---|
| std 1 61 | PDF + ePub | |
| std 2 61 | Paper |
- CHF61
Life cycle
Got a question?
Check out our FAQs
Customer care
+41 22 749 08 88
Opening hours:
Monday to Friday - 09:00-12:00, 14:00-17:00 (UTC+1)