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Generation of fast neutron removal cross sections using a multi-layered spherical shell model
Radiation Physics and Chemistry ( IF 2.9 ) Pub Date : 2021-08-04 , DOI: 10.1016/j.radphyschem.2021.109735
Frederick C. Hila 1 , Julius Federico M. Jecong 1 , Cheri Anne M. Dingle 1 , Geraldine C. Geraldino 2 , Abigaile Mia J. Hila 1 , Neil Raymund D. Guillermo 1
Affiliation  

A new method is explored for estimating the fast or fission neutron removal cross sections in single-element or multi-element media. A spherical Monte Carlo model conforming to the removal theory for fission neutrons was used. The MCNP5 code coupled with ENDF/B-VII.0 library was used to simulate the transport of U-235 fission neutrons within the model. Several removal cross sections were generated for abundant elements in construction and nuclear materials including H, Li, Be, B, C, O, F, Al, Cl, Fe, Ni, Cu, W, Pb, Bi, and U, and multi-element materials such as several compounds and composites. Validations were made using experimentally produced fast neutron removal cross section values, and those given by Phy-X/PSD and MRCsC software, and an empirical method. The comparison of the Monte Carlo generated removal cross sections showed good agreements with experimental values and those by theoretical methods. For multi-element media, the Monte Carlo generated removal cross sections were found to best fit the experimental values, in comparison with those produced by other available methods. Furthermore, a comparison of the thermal fluence trends obtained between the Monte Carlo simulations and several neutron removal experiments resulted in good agreement. The proposed method is highly useful in the generation of ENDF/B based removal cross sections, for point-kernel applications and fast neutron shielding materials comparisons.



中文翻译:

使用多层球壳模型生成快速中子去除截面

探索了一种估计单元素或多元素介质中快速或裂变中子去除截面的新方法。使用符合裂变中子去除理论的球形蒙特卡罗模型。MCNP5 代码与 ENDF/B-VII.0 库相结合,用于模拟模型内 U-235 裂变中子的传输。为建筑和核材料中的丰富元素生成了多个去除截面,包括 H、Li、Be、B、C、O、F、Al、Cl、Fe、Ni、Cu、W、Pb、Bi 和 U,以及多-元素材料,例如几种化合物和复合材料。使用实验产生的快速中子去除截面值、Phy-X/PSD 和 MRCsC 软件给出的值以及经验方法进行了验证。Monte Carlo 生成的去除横截面的比较显示出与实验值和理论方法的良好一致性。对于多元素介质,与其他可用方法产生的相比,蒙特卡罗生成的去除截面被发现最适合实验值。此外,蒙特卡罗模拟和几个中子去除实验之间获得的热注量趋势的比较产生了很好的一致性。所提出的方法在生成基于 ENDF/B 的去除截面、点核应用和快速中子屏蔽材料比较方面非常有用。与其他可用方法生产的产品相比。此外,蒙特卡罗模拟和几个中子去除实验之间获得的热注量趋势的比较产生了很好的一致性。所提出的方法在生成基于 ENDF/B 的去除截面、点核应用和快速中子屏蔽材料比较方面非常有用。与其他可用方法生产的产品相比。此外,蒙特卡罗模拟和几个中子去除实验之间获得的热注量趋势的比较产生了很好的一致性。所提出的方法在生成基于 ENDF/B 的去除截面、点核应用和快速中子屏蔽材料比较方面非常有用。

更新日期:2021-08-10
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