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ANS 19.10
Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals
Organization:
ANS - American Nuclear Society
Year: 2009
Abstract: 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 bottom of the active fuel given the neutron source in the core. This evaluation employs both fast neutron flux computations and measurement data from invessel and cavity dosimetry, as appropriate. The standard applies to both U.S.-designed pressurized water reactors (PWRs) and boiling water reactors (BWRs).
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| contributor author | ANS - American Nuclear Society | |
| date accessioned | 2017-09-04T15:42:52Z | |
| date available | 2017-09-04T15:42:52Z | |
| date copyright | 01/01/2009 | |
| date issued | 2009 | |
| identifier other | PKIKMCAAAAAAAAAA.pdf | |
| identifier uri | https://yse.yabesh.ir/std/handle/yse/45044 | |
| description abstract | 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 bottom of the active fuel given the neutron source in the core. This evaluation employs both fast neutron flux computations and measurement data from invessel and cavity dosimetry, as appropriate. The standard applies to both U.S.-designed pressurized water reactors (PWRs) and boiling water reactors (BWRs). | |
| language | English | |
| title | ANS 19.10 | num |
| title | Methods for Determining Neutron Fluence in BWR and PWR Pressure Vessel and Reactor Internals | en |
| type | standard | |
| page | 14 | |
| status | Active | |
| tree | ANS - American Nuclear Society:;2009 | |
| contenttype | fulltext |