Measurement of leakage neutron spectra for aluminium with D-T fusion neutrons and validation of evaluated nuclear data

Measurement of leakage neutron spectra for aluminium with D-T fusion neutrons and validation of evaluated nuclear data
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用 D-T 聚变中子测量铝的泄漏中子谱并验证评估的核数据

DOI:
10.1016/j.fusengdes.2021.112582
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发表时间:
2021
影响因子:
1.7
通讯作者:
Jiang W.
Jiang W.
中科院分区:
工程技术3区
文献类型:
--
作者:
Zhang S.;Niu D.;Wang D. X.;Nie Y.;Song N.;Wang J. C.;Ruan X.;Huang M.;Wada R.;Ren J.;Ding Y.;Zhang K.;Tang X.;Han R.;Liu B.;Lu L.;Jiang W.

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在本文介绍的积分基准实验中,用氘氚(DT)聚变中子辐照了300 mm× 300 mm× 100 mm的铝(Al)平板样品。用BC 501 A有机液体闪烁体探测样品中泄漏的中子,通过飞行时间(TOF)方法,考虑探测器效率,由TOF曲线得到中子能谱。为了比较,一些泄漏中子谱也通过结合蒙特卡罗中子输运代码与ENDF/B-VIII的评估核数据进行了模拟。0、JENDL-4.0和CENDL-3.1库。除个别能量范围外,所有计算值与实验值的符合率均在10%以内。使用ENDF/B-VIII预测的值。在120 ℃时,CENDL-3.1和JEDNL-4.0库的数据在9.5-12 MeV范围内的差异较大。本文还讨论了造成这些差异的可能原因。
In the integral benchmark experiment presented here, an aluminium (Al) slab sample (300 mm× 300 mm× 100 mm) was irradiated with Deuterium-Tritium (DT) fusion neutrons. The neutrons leaking from the sample were detected by a BC501A organic liquid scintillator through the time-of-flight (TOF) method; the neutron energy spectra were derived from the as-obtained TOF curves by considering the detector efficiency. For comparison, some leakage neutron spectra were also simulated by combining a Monte Carlo neutron transport code with evaluated nuclear data from the ENDF/B-VIII. 0, JENDL-4.0 and CENDL-3.1 libraries. All the calculated values agreed with the experimental data within 10%, except for a few energy ranges. The values predicted using the ENDF/B-VIII. 0 library were lower and higher than the measured ones at below and higher above 4 MeV, respectively; the data based on the CENDL-3.1 and JEDNL-4.0 libraries exhibited some larger differences in the 9.5–12 MeV range at 120∘. The possible causes of these discrepancies are also discussed.
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