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This standard specifies neutron and gamma-ray cross sections and related group-averaged or derived data for the energy range and materials of importance in nuclear radiation protection and shielding calculations for nuclear power plants.
Author | ANS |
---|---|
Editor | ANS |
Document type | Standard |
Format | File |
Confirmation date | 2013-08-28 |
ICS | 27.120.10 : Reactor engineering |
Replace | ANSI/ANS 6.1.2 (1999) |
Year | 2013 |
Document history | ANSI/ANS 6.1.2 (2013) |
Country | USA |
Keyword | ANSI 6;ANSI/ANS 6;6;ANSI/ANS 6.1.2-2013 |