ANS 19.3

Steady-state neutronics methods for power reactor analysis

contributor author	ANS - American Nuclear Society
date accessioned	2017-09-04T16:15:48Z
date available	2017-09-04T16:15:48Z
date copyright	01/01/2011
date issued	2011
identifier other	SYDCTEAAAAAAAAAA.pdf
identifier uri	https://yse.yabesh.ir/std/handle/yse/79104
description abstract	This standard provides guidance for performing and validating the sequence of steady-state calculations leading to prediction—in all types of operating commercial nuclear reactors—of the following: (1) reaction-rate spatial distributions; (2) reactivity; (3) change of nuclide compositions with time. The standard provides the following: (1) guidance for the selection of computational methods; (2) criteria for verification and validation of calculation methods used by reactor core analysts; (3) criteria for evaluation of accuracy and range of applicability of data and methods; (4) requirements for documentation of the preceding. Note that the use of mixed uranium-plutonium oxide (MOX) fuel has been taken as out of scope for this revision of the standard. It will be taken into account in the next revision.
language	English
title	ANS 19.3	num
title	Steady-state neutronics methods for power reactor analysis	en
type	standard
page	38
status	Active
tree	ANS - American Nuclear Society:;2011
contenttype	fulltext