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DEVELOPMENT OF THE 4S AND RELATED TECHNOLOGIES (7) SUMMARY OF THE FCA XXIII EXPERIMENT ANALYSES TOWARDS EVALUATION OF PREDICTION ACCURACIES FOR THE 4S CORE CHARACTERISTICS

机译：开发4S和相关技术（7）FCA XXIII实验概述分析了4S核心特征的预测精度评估

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A series of critical experiments were carried out in the JAEA fast critical facility (FCA) named FCA XXIII cores with placing emphases on the reflector reactivity worth and the sodium void reactivity which are especially important from the view point of safety features of the 4S. The analyses of those physics mockup experiments have been carried out by the neutron transport calculation methods with continuous energy Monte Carlo code MVP and 70 energy-group discrete ordinate P0-S8 transport code DANTSYS using libraries processed from JENDL-3.3 data file. The results showed that combination of the stochastic and deterministic transport calculation methods (Monte Carlo and Sn) provided good prediction bases for criticality, reflector worth, sodium void reactivity, reaction rate ratios and absorber reactivity worth for the 4S nuclear design.

机译：在JAEA快速关键工具（FCA）中进行了一系列关键实验，该设施（FCA）命名为FCA XXIII核心，其重点在于4S的安全特征的视角尤为重要的反射器反应性价值和无效反应性。这些物理模型实验的分析已经通过中子传输计算方法进行了使用从JENDL-3.3数据文件处理的库进行了连续的能量蒙特卡罗代码MVP和70能量组离散纵坐标P0-S8传输代码Dantsys。结果表明，随机和确定性传输计算方法（Monte Carlo和Sn）的组合为4S核设计提供了良好的临界，反射器价值，无空隙反应性，反应速率比和吸收器反应性的良好预测基础。

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《International Congress on Advances in Nuclear Power Plants》|2009年||共9页
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Nobuyuki Ueda; Masahiro Fukushima; Shigeaki Okajima; Toshikazu Takeda; Takanori Kitada; Yasushi Nauchi; Izumi Kinoshita; Tetsuo Matsumura;
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DEVELOPMENT OF THE 4S AND RELATED TECHNOLOGIES (7) SUMMARY OF THE FCA XXIII EXPERIMENT ANALYSES TOWARDS EVALUATION OF PREDICTION ACCURACIES FOR THE 4S CORE CHARACTERISTICS

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