New efficient albedo Monte Carlo method for neutron streaming analyses.

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概要

• 論文の詳細を見る

• An efficient albedo Monte Carlo method newly developed has been studied by analyzing two types of experiments on neutron streaming. The method is characterized by employing the energy-angle dependent doubly differential albedos for slab, which can be calculated in a short computer time with a one-dimensional transport theory, such as the Sn method and more efficient invariant imbedding method. This paper describes the features of the present albedo Monte Carlo method, including fundamental formulas. In the analyses of the neutron streaming experiments, the calculated results agreed with the measured data within a factor of 2 for a benchmark experiment at the YAYOI reactor and within a factor of 3 for an SNR sodium duct mock-up experiment.<BR>It is concluded that the present albedo Monte Carlo method is practical and applicable to the reactor shielding analysis concerning radiation streaming.

• 一般社団法人 日本原子力学会の論文

著者

• NAKAI Masaru

  NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co. Ltd.

• YAMAUCHI Michinori

  NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co. Ltd.

• KAWAI Masayoshi

  NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co. Ltd.

• KAWAI Masayoshi

  NAIG Nuclear Research Laboratory Nippon Atomic Industry Group Co., Ltd.

• HAYASHIDA Yoshihisa

  NAIG Nuclear Research Laboratory, Nippon Atomic Industry Group Co. Ltd.

• 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"
• 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.

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