Development of Sn-AMC-AMC coupling technique and its application to analysis of neutron streaming data of "JOYO"

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概要

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• An Sn-albedo Monte Carlo-albedo Monte Carlo (Sn-AMC-AMC) coupling technique has been developed and implemented in the AMC code system MORSE-ALB in order to make an effective and accurate shielding calculation for large and complex geometry. This paper describes the feature of the present coupling method which includes new source geometry in the Sn-AMC coupling calculation. Applicability of the present method was studied by analyzing the experiments of neutron streaming in "JOYO". The Sn-AMC-AMC coupling calculation reproduced the measured data within the accuracy of one order of magnitude. Considering that neutron fluxes attenuate by 812 orders of magnitude from the core to the measuring positions and the streaming paths are complicated, the agreement can be regarded good.

• 一般社団法人 日本原子力学会の論文

著者

• KAWAI Masayoshi

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

• YAMAUCHI Michinori

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

• NAKAI Masaru

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

• HAYASHIDA Yoshihisa

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

• NIIDOME Jiroh

  Toshiba Corp.

• YAMAUCHI Michinori

  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.

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.

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