Large reactivity transients in dilute plutonium-water solutions
Large reactivity transients in dilute plutonium-water solutions
复制标题
稀钚水溶液中的大反应瞬变
DOI：
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发表时间：
1997
期刊：
影响因子：
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通讯作者：
S. T. Newkirk
中科院分区：
文献类型：
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作者：
D. Hetrick;S. T. Newkirk
在钚处理容器和高放废物储存中发生自催化核漂移的可能性最近受到了一些关注。这种可能行为的一个来源是预测溶液浓度低于20克钚/升时的正中子光谱温度系数。本文的目的是报道一些新的对实际钚溶液组合的动态模拟，并对所涉及的现象提供一些物理见解。先前对假设的钚-水组件的计算使用了我们的模拟模型的早期版本。这些模型最初是为铀水溶液开发的，并以溶液反应堆实验和实验室临界事故模拟为基准。新的钚-水模拟中使用的中子温度系数由Kornreich计算，临界构型数据和体积膨胀反应性系数由Lee和Lee和Hetrick计算。Newkirk的论文中包含了一些最新的动态结果。使用个人计算机仿真语言DESIRE进行计算。
The possibility of autocatalytic nuclear excursions in plutonium processing vessels and high-level waste storage has recently received some attention. One source of such possible behavior is the positive neutron spectral temperature coefficient that is predicted for solution concentrations below 20 g plutonium/l. The purpose of this paper is to report some new dynamic simulations for realistic plutonium solution assemblies and to offer some physical insight into the phenomena involved. Previous computations for hypothetical plutonium-water assemblies used an earlier version of our simulation models. The models were originally developed for uranium-water solutions and benchmarked against solution reactor experiments and laboratory simulations of criticality accidents. Neutron temperature coefficients used in the new plutonium-water simulations were computed by Kornreich, and the critical configuration data and volume expansion reactivity coefficients were computed by Lee and Lee and Hetrick. Some recent dynamic results are included in the thesis by Newkirk. Computations were performed using the personal computer simulation language DESIRE.