Simple model of thermal-hydraulic feedback for the neutronic analysis of PWR cores

S. Kimhy; A. Galperin

doi:10.1016/0306-4549(88)90030-8

Simple model of thermal-hydraulic feedback for the neutronic analysis of PWR cores

S. Kimhy, A. Galperin

Unit of Nuclear Engineering

Research output: Contribution to journal › Article › peer-review

Abstract

A simple model of thermal-hydraulic feedback for the neutronic analysis of a PWR core was developed and implemented into an overall calculational system. A series of numerical experiments were carried out to establish the coefficients of the cross-section adjustment formulas. A benchmark comparison calculations of a ZION-2 (Impink et al., 1979) first-cycle demonstrated the validity of the model and overall improvements of the quality of the neutronic analysis. For PWRs the thermal-hydraulic feedback has a second-order effect on the results of the neutronic analysis, therefore application of the simplified models generate reasonably accurate results. Actual implementation of the model into the BGUCORE calculational system (Galperin et al., 1985) is described and demonstrated.

Original language	English
Pages (from-to)	95-100
Number of pages	6
Journal	Annals of Nuclear Energy
Volume	15
Issue number	2
DOIs	https://doi.org/10.1016/0306-4549(88)90030-8
State	Published - 1 Jan 1988

ASJC Scopus subject areas

Nuclear Energy and Engineering

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10.1016/0306-4549(88)90030-8

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abstract = "A simple model of thermal-hydraulic feedback for the neutronic analysis of a PWR core was developed and implemented into an overall calculational system. A series of numerical experiments were carried out to establish the coefficients of the cross-section adjustment formulas. A benchmark comparison calculations of a ZION-2 (Impink et al., 1979) first-cycle demonstrated the validity of the model and overall improvements of the quality of the neutronic analysis. For PWRs the thermal-hydraulic feedback has a second-order effect on the results of the neutronic analysis, therefore application of the simplified models generate reasonably accurate results. Actual implementation of the model into the BGUCORE calculational system (Galperin et al., 1985) is described and demonstrated.",

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AB - A simple model of thermal-hydraulic feedback for the neutronic analysis of a PWR core was developed and implemented into an overall calculational system. A series of numerical experiments were carried out to establish the coefficients of the cross-section adjustment formulas. A benchmark comparison calculations of a ZION-2 (Impink et al., 1979) first-cycle demonstrated the validity of the model and overall improvements of the quality of the neutronic analysis. For PWRs the thermal-hydraulic feedback has a second-order effect on the results of the neutronic analysis, therefore application of the simplified models generate reasonably accurate results. Actual implementation of the model into the BGUCORE calculational system (Galperin et al., 1985) is described and demonstrated.

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JO - Annals of Nuclear Energy

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Simple model of thermal-hydraulic feedback for the neutronic analysis of PWR cores

Abstract

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