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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 | http://yse.yabesh.ir/std;query=autho162sear/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 |