| 低温供热堆温度系数的计算研究 |
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| 引用本文： | 钟文发,罗经宇.低温供热堆温度系数的计算研究[J].清华大学学报(自然科学版),1994(3). |
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| 作者姓名： | 钟文发 罗经宇 |
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| 作者单位： | 清华大学核能技术设计研究院 |
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| 摘 要： | 本文介绍了供热堆反应性温度系数的计算方法，以２００ＭＷ堆为设计实例，计算了初装堆芯的燃料温度系数和慢化剂温度系数。同时，对于首炉运行工况下的温度系数作了比较细致的计算，这些计算结果为低温堆物理设计提供了科学依据。
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| 关 键 词： | 温度系数 有效倍增因子 供热堆 |
Calculation of temperature coefficient for NHRs |
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| Zhong Wenfa, Luo Jingyu.Calculation of temperature coefficient for NHRs[J].Journal of Tsinghua University(Science and Technology),1994(3). |
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| Authors: | Zhong Wenfa Luo Jingyu |
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| Affiliation: | Institute of Nuclear Energy Technology Tsinghua University |
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| Abstract: | The calculating method of temperature coefficient of reactivity for NHRs ispresented in this paper. An example case has been made for 200MW heating reactor.The fuel and moderator temperature coefficients were calculated for initial -- loaded coreand for the first cycle. The results provide a basis for the reactor safety analysis. |
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| Keywords: | temperature coefficient effective multiplication factor nuclear heating |
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