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对含钨、铀、碳和碳化氢的多板样品组件在D-T中子辐照下泄漏中子谱的测量与分析。

Measurements and analysis of leakage neutron spectra from multiple-slab sample assemblies comprising W,U,C, and CH with D-T neutron irradiation.

作者信息

Luo F, Han R, Chen Z, Nie Y, Sun Q, Shi F, Zhang S, Tian G, Song L, Ruan X, Ye M Y

机构信息

Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China; School of Physical Sciences, University of Science and Technology of China, Hefei 230027, China.

Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China; Key Laboratory of Nuclear Data, China Institute of Atomic Energy, Beijing 102413, China.

出版信息

Appl Radiat Isot. 2018 Jul;137:123-128. doi: 10.1016/j.apradiso.2018.03.014. Epub 2018 Mar 26.

DOI:10.1016/j.apradiso.2018.03.014
PMID:29609052
Abstract

The accelerator driven subcritical system (ADS) is regarded as a safe and clean nuclear power system, which can be used for the transmutation of nuclear waste and the breeding of nuclear fuel. In this study, in order to validate nuclear data and the neutron transportation performance of the materials related to ADS, we measured the leakage neutron spectra from multiple-slab sample assemblies using 14.8 MeV D-T neutrons. Two types of assemblies comprising A-1 (W+U+C+CH) and A-2 (U+C+CH) were both built up gradually starting with the first wall. The measured spectra were compared with those calculated using the Monte Carlo code neutron transport coed (MCNP)-4C. A comparison of the results showed that the experimental leakage neutron spectra for both A-1 or A-2 were reproduced well by the three evaluated nuclear data libraries with discrepancies of less than 15% (A-1) and 12% (A-2), except when below 3 MeV. For 2-cm and 5-cm uranium samples, the CENDL-3.1 calculations exhibited large discrepancies in the energy range of 2-8 MeV and above 13 MeV. Thus, the CENDL-3.1 library for uranium should be reevaluated, especially around this energy range. It was significant that the leakage neuron spectra changed clearly when the latest material layer was added during the building of assemblies A-1 and A-2.

摘要

加速器驱动次临界系统(ADS)被视为一种安全、清洁的核电系统,可用于核废料嬗变和核燃料增殖。在本研究中,为了验证与ADS相关的核数据和材料的中子输运性能,我们使用14.8兆电子伏特的D-T中子测量了多板样品组件的泄漏中子能谱。两种组件,包括A-1(W+U+C+CH)和A-2(U+C+CH),都是从第一壁开始逐步构建的。将测量的能谱与使用蒙特卡罗代码中子输运代码(MCNP)-4C计算的能谱进行了比较。结果比较表明,除了在3兆电子伏特以下,A-1或A-2的实验泄漏中子能谱在三个评估核数据库中都得到了很好的再现,差异小于15%(A-1)和12%(A-2)。对于2厘米和5厘米的铀样品,CENDL-3.1计算在2-8兆电子伏特和13兆电子伏特以上的能量范围内存在较大差异。因此,应重新评估铀的CENDL-3.1库,特别是在这个能量范围附近。重要的是,在构建组件A-1和A-2的过程中添加最新材料层时,泄漏中子能谱发生了明显变化。

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