Transport Criticality Analysis of FBR MONJU Initial Critical Core in Whole Core Simulation by NSHEX and GMVP

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概要

• 論文の詳細を見る

• The Japanese prototype fast breeder reactor MONJU developmental project is of prime importance in the establishment of the commercialized fast breeder reactor technology in Japan. This work presents new results obtained by the 3D hexagonal transport nodal code NSHEX, which for the first time has been applied to MONJU criticality analysis in whole core simulation and up to 70 energy groups. Significant energy-group approximation effect on keff caused by the collapsing into coarse energy-group structure has been found and then confirmed separately using the Monte Carlo analysis. On the basis of the presented applied results, a method of transport correction evaluation, based on 70 energy-group approximation can be recommended instead of the conventional few-group method that assumes inter-independency of energy-group approximation and transport effect.

• 社団法人 日本原子力学会の論文
• 2004-04-25

著者

• Todorova G

  Core Development Group International Cooperation And Technology Development Center Tsuruga Head Offi

• TODOROVA Galina

  Core Development Group, International Cooperation and Technology Development Center, Tsuruga Head Of

• NISHI Hiroshi

  Core Development Group, International Cooperation and Technology Development Center, Tsuruga Head Of

• ISHIBASHI Junichi

  Core Development Group, International Cooperation and Technology Development Center, Tsuruga Head Of

• Nishi H

  Japan Nuclear Cycle Dev. Inst. Fukui

• Nishi Hiroshi

  Core Development Group International Cooperation And Technology Development Center Tsuruga Head Offi

• Ishibashi Junichi

  Core Development Group International Cooperation And Technology Development Center Tsuruga Head Offi

関連論文

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• 「もんじゅ」初臨界炉心臨界性の輸送計算解析--3次元ノード法Sn輸送計算コードNSHEX及びモンテカルロ輸送計算コードGMVPによる
• Method for Condensation of the Macroscopic Transport Cross-Sections for Criticality Analyses of FBR MONJU by the Code NSHEX
• Transport Criticality Analysis of FBR MONJU Initial Critical Core in Whole Core Simulation by NSHEX and GMVP
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