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This standard provides criteria for performing and validating the sequence of calculations required for the prediction of the fast neutron fluence t in the reactor vessel. Applicable to PWR and BWR plants the standard addresses flux attenuation from the core through the vessel to the cavity and provides criteria for generating cross sections, spectra, transport and comparisons with in- and ex-vessel measurements, validation, uncertainties and flux extrapolation to the inside vessel surface.
Author | ANS |
---|---|
Editor | ANS |
Document type | Standard |
Format | File |
Confirmation date | 2016-10-11 |
ICS | 27.120.10 : Reactor engineering |
Cross references | ISO 19226 (2017-11), NEQ |
Year | 2009 |
Document history | |
Country | USA |
Keyword | ANSI 19;ANSI/ANS 19;19;ANSI/ANS 19.10-2009 (R2016) |