ANS 19.3
Steady-state neutronics methods for power reactor analysis
Organization:
ANS - American Nuclear Society
Year: 2011
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.
(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.
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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 |