ANS 19.10-2009(R2016) (R2021)

ANS 19.10-2009(R2016) (R2021)

Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals

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Details

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).

Additional Info

Author American Nuclear Society
Published by ANS
Document type Standard
Theme /subgroups/55485
Confirmation date 2021-01-01
Number of pages 14
Keyword ANS 19.10-2009 (R2016)
ANSI Approved