Temperature Coefficient of Reactivity in Light-Water Moderated and Reflected Cores Loaded with Highly-Enriched-Uranium Fuel
Temperature Coefficient of Reactivity in Light-Water Moderated and Reflected Cores Loaded with Highly-Enriched-Uranium Fuel
复制标题
装载高浓铀燃料的轻水慢化和反射堆芯的反应温度系数
DOI：
10.1080/18811248.1987.9735861
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发表时间：
1987
影响因子：
1.2
通讯作者：
K. Kanda
中科院分区：
文献类型：
--
作者：
M. Mori;S. Shiroya;K. Kanda
在京都大学临界装置建造的装有高浓缩铀燃料的轻水慢化和反射堆芯中，对反应性温度系数进行了实验和分析研究。在20 - 70°C范围内测量温度对反应性的影响，以分别研究（1）燃料沥青（H/235 U原子比）和（2）堆芯形状对该物理量的影响。利用SRAC程序系统对实验数据进行了分析。计算的特征值keff同意与测量的一个在0.5%以内的C/E比的2-和3-维扩散计算。通过本征值和微扰计算近似再现了实验数据。结果表明，芯区对反应性温度系数的贡献为负，而反射区的贡献为正。这些贡献的综合使温度变化成为可能。
Both experimental and analytical studies have been performed on the temperature coefficient of reactivity in a light-water moderated and reflected core loaded with highly-enriched-uranium fuel, which was constructed in the Kyoto University Critical Assembly (KUCA). The temperature effect on reactivity was measured for the range of 20∼70°C to investigate separately the effects of (1) the fuel pitch (H/235U atomic ratio) and (2) the core shape on this physical quantity. The experimental data were analyzed with use of the SRAC code system. The calculated eigenvalue k eff agreed with the measured one within 0.5% in the C/E ratio for both the 2- and 3-dimensional diffusion calculations. The experimental data were approximately reproduced by both the eigenvalue and perturbation calculations. It was found that the contribution of the core region was negative to the temperature coefficient of reactivity, whereas that of the reflector region was positive. The synthesis of these contributions made the temperature c...