Nom | Support | Langue | Disponibilité | Date d'édition | Prix | ||
---|---|---|---|---|---|---|---|
PDF |
Anglais |
Active |
24/02/2009 |
78,00 € |
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Détails
This standard provides a procedure for the evaluation of the best-estimate fast (E > 1.0 MeV) neutron fluence in the annular region between the core and the inside surface of the vessel, through the pressure vessel and the reactor cavity, between the top and bot-tom of the active fuel given the neutron source in the core. This evaluation employs both fast neutron flux computations and measurement data from in-vessel and cavity dosimetry, as appropriate. The standard applies to both U.S.-designed pressurized water reactors (PWRs) and boiling water reactors (BWRs).
Informations supplémentaires
Auteur | American Nuclear Society |
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Edité par | ANS |
Type de document | Norme |
Thème | /subgroups/55485 |
Date de confirmation | 2021-01-01 |
Nombre de pages | 14 |
Mot-clé | ANS 19.10-2009 (R2016) |
ANSI Approved |