Monte Carlo Perturbation Analysis of Isothermal Temperature Reactivity Coefficient in Kyoto University Critical Assembly
2015 · Nuclear Technology
저자
Byoung Kyu Jeon, Cheol Ho Pyeon, 심형진 (Hyung Jin Shim)
연구주제
Nuclear reactor physics and engineering · Nuclear Engineering Thermal-Hydraulics
NTIS 과학기술표준분류
에너지/자원만에너지·환경·원자력 확장
지원 과제·AI 키워드로 잡을 근거가 없어 분류하지 않았다.
AI 연구 키워드·방법
isothermal temperature coefficient 교토대학 임계집합체(KUCA) 반응도 계수
키워드 (OpenAlex)
Kyoto University Critical Assembly D2O moderator
초록
Experiments on the isothermal temperature reactivity coefficient (ITRC) have been carried out at the light water–moderated core with or without a D2O tank in the Kyoto University Critical Assembly. The ITRC experiments are analyzed by a continuous-energy Monte Carlo (MC) neutron transport analysis code, McCARD. Through the temperature changes of H2O and D2O, effects of the coolant density changes in moderator and reflector regions and the microscopic cross-section variations on the ITRC are investigated by sensitivity analyses with the use of the MC adjoint-weighted perturbation method. An adjoint-weighted correlated sampling method for the stochastic mixing technique of cross-section libraries is devised to estimate the reactivity change from a perturbation of the thermal scattering cross sections due to the temperature change. From results of the MC perturbation analyses, it is clearly…
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Nuclear reactor physics and engineering