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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 1,291 - 1,302 (12page)
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This paper presents a new and efficient scheme to determine the optimal neutron sourceposition in a model near-equilibrium pressurized water reactor, which is based on theOPR1000 Hanul Unit 3 Cycle 7 configuration. The proposed scheme particularly assignsimportance of source positions according to the local adjoint flux distribution. In thisresearch, detailed pin-by-pin reactor adjoint fluxes are determined by using the MonteCarlo KENO-VI code from solutions of the reactor homogeneous critical adjoint transportequations. The adjoint fluxes at each allowable source position are subsequently ranked toyield four candidate positions with the four highest adjoint fluxes. The study next simulatesex-core detector responses using the Monte Carlo MAVRIC code by assuming aneutron source is installed in one of the four candidate positions. The calculation isrepeated for all positions. These detector responses are later converted into an inversecount rate ratio curve for each candidate source position. The study confirms that theoptimal source position is the one with very high adjoint fluxes and detector responses,which is interestingly the original source position in the OPR1000 core, as it yields an inversecount rate ratio curve closest to the traditional 1/M line. The current work also clearlydemonstrates that the proposed adjoint flux-based approach can be used to efficientlydetermine the optimal geometry for a neutron source and a detector in a modern pressurizedwater reactor core.
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참고문헌 (18)
참고문헌 신청
Nuclear Power Generation Department / 1998 / Safety Evaluation for a Startup Operation without Neutron Source of Kori Unit 1 / Korea Electric Power Company, LTD
J.S. Chung / 2005 / The Nuclear Design Report for Ulchin Nuclear Power Plant Unit 3 Cycle 7
W. Bojduj / 2010 / Source Range Detector Response during Boron Dilution Accident at Shutdown / American Nuclear Society:2010 Annual Meeting :517~518
Y.A. Chao / 2004 / The Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical Reactivity Measurement / American Nuclear Society: 2004 Annual Meeting :728~730
C.A. Ford / 2010 / Modeling a Source Range Channel Response during a PWR Core Onload Sequence / American Nuclear Society: 2010 Annual Meeting :639~641
J.S. Chung / 2005 / The Nuclear Design Report for Ulchin Nuclear Power Plant Unit 3 Cycle 7
W. Bojduj / 2010 / Source Range Detector Response during Boron Dilution Accident at Shutdown / American Nuclear Society:2010 Annual Meeting :517~518
Y.A. Chao / 2004 / The Spatially Corrected Inverse Count Rate (SCICR) Method for Subcritical Reactivity Measurement / American Nuclear Society: 2004 Annual Meeting :728~730
C.A. Ford / 2010 / Modeling a Source Range Channel Response during a PWR Core Onload Sequence / American Nuclear Society: 2010 Annual Meeting :639~641
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