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Verification of JUPITER standard analysis method for upgrading Joyo MK-III core design and management

高速実験炉「常陽」の炉心設計・炉心管理高度化のためのJUPITER標準解析手法の検証

前田 茂貴; 伊藤 主税; 関根 隆; 青山 卓史

Maeda, Shigetaka; Ito, Chikara; Sekine, Takashi; Aoyama, Takafumi

高速実験炉「常陽」の炉心設計・炉心管理高度化のためのJUPITER標準解析手法の検証を、MK-III性能試験及び定格運転サイクルにおける炉物理試験結果を用いて実施した。解析結果と実験値との比は、5%以内とよく一致した。この比較を通じて、JUPITER標準解析手法の「常陽」MK-III炉心における計算精度を確認した。本研究の結果、制御棒価値をはじめとする核特性の設計裕度が合理化できる。これにより、燃料交換体数を節約した効率的な炉心設計・炉心管理が実施でき、節約した燃料により多くの照射試験が実施可能となる。

The verification of calculated core characteristics of the Joyo MK-III core using the JUPITER fast reactor standard analysis method was conducted by comparing with the measured values through the core physics tests. The purpose is to upgrade the core performance to increase the driver fuel burn-up and to increase the excess reactivity necessary for conducting various irradiation tests in the core region. Most of the C/Es are within 5% of unity. Through the comparisons, the calculation accuracy of the JUPITER standard analysis method for a small size sodium cooled fast reactor with a hard neutron spectrum like Joyo was clarified. As a result of this study, more irradiation tests can be performed with appropriate safety margin and the efficient core and fuel management can be achieved to save the number of refueling.

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