Development of an asymmetric multiple-position neutron source (AMPNS) method to monitor the criticality of a degraded reactor core
Identifieur interne : 002673 ( Istex/Corpus ); précédent : 002672; suivant : 002674Development of an asymmetric multiple-position neutron source (AMPNS) method to monitor the criticality of a degraded reactor core
Auteurs : S. H. Levine ; S. S. KimSource :
- Annals of Nuclear Energy [ 0306-4549 ] ; 1985.
Abstract
Tne analytical/experimental method has been developed to to monitor the subcritical reactivity and unfold the k∞ distribution of a degraded reactor core. The method uses several fixed neutron detectors and a 252Cfneutron source placed sequentially in multiple positions in the core. Therefore, it is called the asymmetric multiple-position neutron source (AMPNS) method. The AMPNS method employs the nucleonic codes to analyze in two dimensions the neutron multiplication of a 252Cf neutron source. An optimization program, GPM, was utilized to unfold the k∞ distribution of the degraded core, in which the desired performance measure minimizes the error between the calculated and the measured count rates of the degraded reactor core. The analytical/experimental approach is validated by performing experiments using the Penn. State Breazeale TRIGA reactor (PSBR). A significant result of this study has been to provide a means to plan the source and detector placements and assign core cells to the damaged TMI-2 core as well as to monitor the criticality during the recovery period.
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DOI: 10.1016/0306-4549(85)90026-X
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<front><div type="abstract" xml:lang="en">Tne analytical/experimental method has been developed to to monitor the subcritical reactivity and unfold the k∞ distribution of a degraded reactor core. The method uses several fixed neutron detectors and a 252Cfneutron source placed sequentially in multiple positions in the core. Therefore, it is called the asymmetric multiple-position neutron source (AMPNS) method. The AMPNS method employs the nucleonic codes to analyze in two dimensions the neutron multiplication of a 252Cf neutron source. An optimization program, GPM, was utilized to unfold the k∞ distribution of the degraded core, in which the desired performance measure minimizes the error between the calculated and the measured count rates of the degraded reactor core. The analytical/experimental approach is validated by performing experiments using the Penn. State Breazeale TRIGA reactor (PSBR). A significant result of this study has been to provide a means to plan the source and detector placements and assign core cells to the damaged TMI-2 core as well as to monitor the criticality during the recovery period.</div>
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