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Copper neutron transport libraries validation by means of a 252Cf standard neutron source
Nuclear Engineering and Technology ( IF 2.6 ) Pub Date : 2021-05-07 , DOI: 10.1016/j.net.2021.04.029
Martin Schulc , Michal Košťál , Evžen Novák , Jan Šimon

Copper is an important structural material in various nuclear energy applications, therefore the correct knowledge of copper cross sections is crucial. The presented paper deals with a validation of different copper transport libraries by means of activation of selected samples. An intense 252Cf(sf) source with a reference neutron spectrum was used as a neutron source. After irradiation, the samples were measured using a high purity germanium detector and the dosimeter reaction rates were inferred. These experimental data were compared with MCNP6 calculations using CENDL-3.1, JENDL-4.0, ENDF/B-VII.1, ENDF/B-VIII.0, JEFF-3.2 and JEFF-3.3 evaluated Cu transport libraries. The experiment specifically focuses on 58Ni(n,p)58Co, 93Nb(n,2n)92mNb, 197Au(n,g)198Au and 55Mn(n,g)56Mn dosimetry reactions. Evaluated activation cross sections of these dosimetric reactions were taken from the IRDFF-II library. The best library performance depends on the energy region of interest.



中文翻译:

通过 252Cf 标准中子源验证铜中子传输库

铜是各种核能应用中的重要结构材料,因此正确了解铜横截面至关重要。所提出的论文通过激活选定的样本来验证不同的铜传输库。具有参考中子谱的强252 Cf(sf) 源用作中子源。辐照后,使用高纯度锗探测器测量样品并推断剂量计反应速率。这些实验数据与使用 CENDL-3.1、JENDL-4.0、ENDF/B-VII.1、ENDF/B-VIII.0、JEFF-3.2 和 JEFF-3.3 评估 Cu 传输库的 MCNP6 计算进行比较。实验特别关注58 Ni(n,p) 58 Co, 93 Nb(n,2n)92m Nb、197 Au(n,g) 198 Au 和55 Mn(n,g) 56 Mn 剂量测定反应。这些剂量反应的评估活化横截面取自 IRDFF-II 库。最佳库性能取决于感兴趣的能量区域。

更新日期:2021-05-07
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