Name | Support | Language | Availability | Edition date | Price | ||
---|---|---|---|---|---|---|---|
PDF |
English |
Active |
2/24/2009 |
€78.00 |
|
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 |
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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 |