No products
New product
This standard provides requirements and guidelines for validation,including establishing applicability, of neutron transport calculational methods used in determining critical or subcritical conditions for nuclear criticality safety analyses.
Author | ANS |
---|---|
Editor | ANS |
Document type | Standard |
Format | File |
Confirmation date | 2017-12-12 |
ICS | 27.120.10 : Reactor engineering |
Replace | ANSI/ANS 8.24 (2007) |
Year | 2017 |
Document history | ANSI/ANS 8.24 (2017) |
Country | USA |
Keyword | ANSI 8;ANSI/ANS 8;8;ANSI/ANS 8.24-2017 |