Benchmark experiment on analytical mock-ups with graphite to simulate the fission blanket of hybrid reactor

Benchmark experiment on analytical mock-ups with graphite to simulate the fission blanket of hybrid reactor
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石墨分析模型模拟混合反应堆裂变包层的基准实验

DOI:
10.1016/j.fusengdes.2019.05.025
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发表时间:
2019-08
影响因子:
1.7
通讯作者:
Liu Rong
Liu Rong
中科院分区:
工程技术3区
文献类型:
--
作者:
Zhu Tonghua;Lu Xinxin;Han Zijie;Jiang Li;Wang Mei;Wen Zhongwei;Liu Rong

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为了验证聚变裂变混合体中子学概念能量倍增的核数据,设计并实施了一个新的中子学实验。作为系列实验的一部分,本文报道了以石墨(C)为反射层,铁(Fe)为第一壁的裂变包层组件(FBA)分析模型的裂变率研究。使用板裂变室(PFC)进行测量。贫铀PFC中的裂变材料与模型中的裂变材料完全相同。用MCNP 5和ENDF/BV.0、ENDF/B-VII.0、JENDL-3.3和CENDL-3.1四个库完成了Monte Carlo计算,并与实验结果进行了比较。裂变率的实验剖面与计算结果符合得很好。用JENDL-3.3计算的结果足以预测10%贫化铀的裂变率。当FBA/C组件中加入铁层时,所有的浓缩铀计算结果都高估了实验结果。Deu裂变率和Enu裂变率的C/E值之间的较大差异可能是由铀的中子散射数据引起的。
To validate the nuclear data in evaluating the energy multiplication of neutronic concept of fusion fission hybrid, a new neutronics experiment has been designed and carried out. As a part of the series experiments, in this work, the fission rate study on the analytical mockups of Fission Blanket Assembly (FBA) with graphite (C) as reflector and with iron (Fe) as first wall was reported. The measurement was conducted with Plate Fission Chambers (PFC). The fissile material in the depleted uranium PFC is strictly the same as that in the mockups. The Monte Carlo calculation with MCNP5 and four libraries ENDF/BV.0, ENDF/B-VII.0, JENDL-3.3 and CENDL-3.1 was finished and compared with the experiment. The profile of fission rates in experiment agreed well with calculation. The calculation with JENDL-3.3 is sufficient to predict fission rates of depleted uranium in 10%. all calculated results of enriched uranium overestimate experimental ones when iron layer was added to the FBA/C assembly. The considerable discrepancy between the C/Es of Deu fission rates and Enu fission rates maybe caused by the neutron scattering data of uranium.
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