Published May 1998 | Version v1
Journal article

Estimation of subcriticality with the computed values analysis using MCNP of experiment on coupled cores

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

Description

Experiments on coupled cores performed at TCA were analysed using continuous energy Monte Carlo calculation code MCNP 4A. Errors of neutron multiplication factors are evaluated using Indirect Bias Estimation Method proposed by authors. Calculation for simulation of pulsed neutron method was performed for 17 X 17 + 5G + 17 x 17 core system and its of exponential experiment method was also performed for 16 x 9 + 3G + 16 x 9 and 16 x 9 + 5G + 16 x 9 core systems. Errors of neutron multiplication factors are estimated to be (-1.5) - (-0.6)% evaluated by Indirect Bias Estimation Method. Its errors evaluated by conventional pulsed neutron method and exponential experiment method are estimated to be 7%, but it is below 1% for estimation of subcriticality with the computed values by applying Indirect Bias Estimation Method. Feasibility of subcriticality management is higher by application of the method to full scale fuel strage facility. (author)

Availability note (English)

Available from DOI: https://doi.org/10.3327/jaesj.40.380

Abstract (Japanese)

TCAで実施された二分割結合炉心実験の解析をMCNP4Aで行った。中性子増倍率の誤差は、筆者らによって提案された「計算誤差間接推定法」で評価した。パルス中性子法シミュレーション計算は17 x 17 + 5G + 17 x 17体系に対して、指数実験法シミュレーションの計算は16 x 9 + 3G + 16 x 9体系及び16 x 9 + 5G + 16 x 9体系に対して行った。「計算誤差間接推定法」による評価によれば、MCNP4Aで計算した中性子増倍率には、0.4∼0.9%の誤差が見込まれる。従来のパルス中性子法及び指数実験法では中性子増倍率に6%の誤差が見込まれているが、「計算誤差間接推定法」による計算値を用いた未臨界度の評価ではそれを1%以下にできる。(日本)

Additional details

Additional titles

Original title (Japanese)
計算値を用いた未臨界度の推定 MCNPによる2分割結合炉心実験の解析

Identifiers

Publishing Information

Journal Title
Nippon Genshiryoku Gakkai-Shi
Journal Volume
40
Journal Issue
5
Journal Page Range
p. 380-386
ISSN
0004-7120

Optional Information

Notes
This record replaces 29053036