지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
초록· 키워드
오류제보하기
Self-powered neutron detector (SPND) is being widely used to monitor the reactor core of the nuclear power plants. The SPND contains a neutron-sensitive metallic emitter surrounded by a ceramic insulator. Currently, the vanadium (V) SPND has been being developed to be used in OPR1000 nuclear power plants. Some Monte Carlo simulations were accomplished to calculate the initial sensitivity of vanadium emitter material and alumina insulator with a cylindrical geometry. An MCNP code was used to simulate some factors (neutron self-shielding factor and beta escape probability from the emitter) and space charge effect of an insulator necessary to calculate the sensitivity of vanadium detector. The simulation results were compared with some theoretical and experimental values. The method presented here can be used to analyze the optimum design of the vanadium SPND and contribute to the development of TMI (Topmount In-core Instrumentation) which might be used in the SMART and SMR.
목차
등록된 정보가 없습니다.
참고문헌 (7)
참고문헌 신청
John W. Hilborn / 1964 / Self-Powered Neutron Detectors for Reactor Flux Monitoring / Nucleonics 22(2)
H. D. Warren / 1972 / Calculational model for self-powered neutron detector / Nucl. Sci. Eng. 48:331
W. Jaschik / 1974 / Model for calculating promptresponse self-powered neutron detectors / Nucl. Sci. Eng. 53:61
H. D. Warren / 1974 / Neutron and gamma-ray effects on self-powered in-core radiation detectors / Nucl. Sci. Eng. 54:395
L. L. Carter / 1982 / Self-Shielding factors for FFTF flux measurements / Trans. Am. Nucl. Soc. 43:710
H. D. Warren / 1972 / Calculational model for self-powered neutron detector / Nucl. Sci. Eng. 48:331
W. Jaschik / 1974 / Model for calculating promptresponse self-powered neutron detectors / Nucl. Sci. Eng. 53:61
H. D. Warren / 1974 / Neutron and gamma-ray effects on self-powered in-core radiation detectors / Nucl. Sci. Eng. 54:395
L. L. Carter / 1982 / Self-Shielding factors for FFTF flux measurements / Trans. Am. Nucl. Soc. 43:710
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