Fission blanket benchmark experiment on spherical assembly of uranium and PE with PE reflector

Fission blanket benchmark experiment on spherical assembly of uranium and PE with PE reflector
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DOI:
10.1016/j.fusengdes.2016.02.054
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发表时间:
2016-04
影响因子:
1.7
通讯作者:
T. Zhu;Xinxin Lu;Mei Wang;Z. Han;Li Jiang;Z. Wen;Rong Liu
T. Zhu;Xinxin Lu;Mei Wang;Z. Han;Li Jiang;Z. Wen;Rong Liu
中科院分区:
工程技术3区
文献类型:
--
作者:
T. Zhu;Xinxin Lu;Mei Wang;Z. Han;Li Jiang;Z. Wen;Rong Liu

文献摘要

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提出了聚变-裂变混合体发电的新概念。为了验证混合包层的核性能,作为验证实验的一部分,本工作建立了两种类型的裂变包层组件,利用平板裂变室(PFC)测量了贫铀-聚乙烯球形组件中铀裂变的反应率分布。实验中有两个PFC,一个是贫铀室,另一个是浓缩铀室。利用蒙特-卡罗输运程序MCNP 5和连续能量截面程序库ENDF/BV. 0分析了两种组件的裂变率分布。计算结果与实验结果进行了比较。贫铀和浓缩铀的裂变速率在两个组件的内边界处都被高估了。但是,C/E比随着离堆芯距离的增加而略有降低的趋势,并且浓缩铀的结果好于贫化铀。
New concept of fusion-fission hybrid for energy generation has been proposed. To validate the nuclear performance of fission blanket of hybrid, as part of series of validation experiment, two types of fission blanket assemblies were setup in this work and measurements were made of the reaction rate distribution for uranium fission in the spherical assembly of depleted uranium and polyethylene by Plate Fission Chamber (PFC). There are two PFCs in experiment, one is depleted uranium chamber and the other is enriched uranium chamber. The Monte-Carlo transport code MCNP5 and continuous energy cross sections library ENDF/BV.0 were used for the analysis of fission rate distribution in the two types of assemblies. The calculated results were compared with the experimental ones. The overestimation of fission rate for depleted uranium and enriched uranium were found in the inner boundary of the two assemblies. However, the C/E ratio tends to decrease for the distance from the core slightly and the results for enriched uranium are better than that for depleted uranium.