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ANS 19.3

Steady-state neutronics methods for power reactor analysis

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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.
URI: https://yse.yabesh.ir/std/handle/yse/79104
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    ANS 19.3

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contributor authorANS - American Nuclear Society
date accessioned2017-09-04T16:15:48Z
date available2017-09-04T16:15:48Z
date copyright01/01/2011
date issued2011
identifier otherSYDCTEAAAAAAAAAA.pdf
identifier urihttps://yse.yabesh.ir/std/handle/yse/79104
description abstractThis 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.
languageEnglish
titleANS 19.3num
titleSteady-state neutronics methods for power reactor analysisen
typestandard
page38
statusActive
treeANS - American Nuclear Society:;2011
contenttypefulltext
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