Applicability of albedo-Sn transport method to analysis of radiation shielding problem.
スポンサーリンク
概要
- 論文の詳細を見る
Albedo-Sn method was developed to predict the angular flux near the coupling boundary in the bootstrap method, using the energy-and-angle dependent double differential albedo boundary condition. In order to verify the applicability of the method to the reactor shielding design, two types of shielding problem have been analyzed. First, the neutron skyshine dose rates measured at the YAYOI reactor in University of Tokyo are predicted within an accuracy of 20%. It is also found that the neutron spectrum in the air-over-ground is much affected by albedo reflection from the ground and is reproduced well by the albedo-Sn method. Second, as for the neutron streaming through a sodium pipe chase-way, the albedo-Sn calculation saves a computer time and gives the results which agree with those by the reference Sn calculation.
- 一般社団法人 日本原子力学会の論文
著者
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KAWAI Masayoshi
NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co., Ltd.
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HAYASHIDA Yoshihisa
NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co., Ltd.
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UEMATSU Mikio
NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co., Ltd.
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KAWAI Masayoshi
NAIG Nuclear Research Laboratory Nippon Atomic Industry Group Co., Ltd.
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HAYASHIDA Yoshihisa
NAIG Nuclear Research Laboratory Nippon Atomic Industry Group Co., Ltd.
関連論文
- Calculation of gamma-ray production cross sections at neutron energies of 1-20 MeV.
- Calculation of neutron albedos for slab with invariant imbedding method.
- Development of Sn-AMC-AMC coupling technique and its application to analysis of neutron streaming data of "JOYO"
- Energy-space dependent error propagation in Monte Carlo coupling calculation.
- Evaluation of neutron cross section of 27 fission product nuclides important for fast reactor.
- Development of albedo-Sn transport method to analyze radiation shielding problem.
- Applicability of albedo-Sn transport method to analysis of radiation shielding problem.
- Systematics of neutron total cross sections of fission product nuclei and optical model fit.
- Development of general next event surface crossing estimators for Monte Carlo method.
- New efficient albedo Monte Carlo method for neutron streaming analyses.