The benchmark experiment on slab beryllium with D–T neutrons for validation of evaluated nuclear data
The benchmark experiment on slab beryllium with D–T neutrons for validation of evaluated nuclear data
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DOI：
10.1016/j.fusengdes.2016.01.049
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发表时间：
2016-04
影响因子：
1.7
通讯作者：
Y. Nie;J. Ren;X. Ruan;J. Bao;R. Han;S. Zhang;H. Huang;X. Li;Y. Ding;H. Wu;P. Liu;Z. Zhou
中科院分区：
文献类型：
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作者：
Y. Nie;J. Ren;X. Ruan;J. Bao;R. Han;S. Zhang;H. Huang;X. Li;Y. Ding;H. Wu;P. Liu;Z. Zhou
铍是未来聚变动力堆固体增殖包层最受青睐的中子倍增器候选材料。然而，铍核数据在现代核数据评价中的呈现方式不同。为了验证铍的评价核数据，在本研究中，在中国原子能科学研究院（CIAE）的基准实验已经完成。用飞行时间法测量了纯铍板样品在61°和121°的中子泄漏谱。利用CENDL-3.1、ENDF/B-VII.1和JENDL-4.0数据库中铍的计算数据，将实验结果与MCNP-4 B模拟结果进行了比较。从测量谱和计算谱之间的比较中发现，基于CENDL-3.1的计算结果在61°下导致高估了大约3-12 MeV的能量范围，而在121°下，所有库导致低估低于3 MeV。
Beryllium is the most favored neutron multiplier candidate for solid breeder blankets of future fusion power reactors. However, beryllium nuclear data are differently presented in modern nuclear data evaluations. In order to validate the evaluated nuclear data on beryllium, in the present study, a benchmark experiment has been performed at China Institution of Atomic Energy (CIAE). Neutron leakage spectra from pure beryllium slab samples were measured at 61° and 121° using time-of-flight method. The experimental results were compared with the calculated ones by MCNP-4B simulation, using the evaluated data of beryllium from the CENDL-3.1, ENDF/B-VII.1 and JENDL-4.0 libraries. From the comparison between the measured and the calculated spectra, it was found that the calculation results based on CENDL-3.1 caused overestimation in the energy range from about 3–12 MeV at 61°, while at 121°, all the libraries led to underestimation below 3 MeV.