ANS 19.10

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

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