Benchmark Experiment on Vanadium with D-T Neutrons and Validation of Evaluated Nuclear Data Libraries by Analysis of the Experiment

Benchmark Experiment on Vanadium with D-T Neutrons and Validation of Evaluated Nuclear Data Libraries by Analysis of the Experiment
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钒的 D-T 中子基准实验和通过实验分析验证评​​估的核数据库

DOI:
10.1080/18811248.1999.9726204
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发表时间:
1999
期刊:
影响因子:
--
通讯作者:
A. Takahashi
A. Takahashi
中科院分区:
--
文献类型:
--
作者:
F. Maekawa;Y. Kasugai;C. Konno;I. Murata;Kokooo;M. Wada;Y. Oyama;Y. Ikeda;A. Takahashi

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利用FNS/JAERI的D-T中子源装置对低活化聚变反应堆材料钒进行了中子学基准实验。在钒实验装置中测量了中子能谱、剂量测定反应速率、γ 射线能谱和 γ 射线加热速率。通过分析实验,对四个评估的核数据文件进行了基准测试。结果,鉴于聚变反应堆设计的准确性,指出了以下问题。 (1) JENDL-FF 和 JENDL-3.2:应重新检查总横截面,尤其是在~2keV 下。 (2) ENDF/B-VI:由于连续中子发射的各向同性角分布,应修改 14 MeV 中子的双微分截面。伽马射线产生截面太小,离散的伽马射线峰无法清楚地表示。 (3) EFF-3:伽马射线产生截面太大。
A neutronics benchmark experiment on vanadium, which is a low activation fusion reactor material, was conducted by using the D-T neutron source facility of FNS/JAERI. Neutron spectra, dosimetry reaction rates, γ-ray spectra and γ-ray heating rates were measured in a vanadium experimental assembly. Benchmark tests for four evaluated nuclear data files were performed by analyzing the experiment. As a result, the following problems were pointed out in view of accuracy of fusion reactor designs. (1) JENDL-FF and JENDL-3.2: Total cross section should be reexamined especially at ∼2keV. (2) ENDF/B-VI: Double differential cross sections for 14 MeV neutrons should be revised because of the isotropic angular distribution for continuum neutron emission. Gamma-ray production cross sections are too small and discrete γ-ray peaks are not represented clearly. (3) EFF-3: Gamma-ray production cross sections are too large.