Monte Carlo Calculations of Fast Neutron Transport in Chloride Salts

Ondřej Šť astný, D. Král, Kamil Števanka, K. Katovský, A. Krása
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Abstract

The purpose of this study is to provide data for optimization of an experimental campaign that is under preparation within the frame of the ADAR project (Accelerator Driven Advanced Reactor with molten chloride salt fuel coolant). This article presents results of theoretical investigation of fast neutron field behavior in chloride salt environment. Non-fueled salt coolant (NaCl, KCl, MgCl2) as well as subcritical fuel-containing (PuCl3) one were considered. As an external neutron source, the radio-isotope AmBe source was modelled. Monte Carlo calculations were performed using the MCNP6.2 code with the ENDF/B-VIII.0 and JEFF-3.3 nuclear data libraries.
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快中子在氯化物盐中输运的蒙特卡罗计算
本研究的目的是为ADAR项目(使用熔融氯盐燃料冷却剂的加速器驱动先进反应堆)框架内正在准备的实验活动提供优化数据。本文介绍了快中子在氯化物盐环境中场行为的理论研究结果。考虑了非燃料盐冷却剂(NaCl, KCl, MgCl2)和亚临界含燃料冷却剂(PuCl3)。作为外源中子源,对放射性同位素AmBe源进行了建模。蒙特卡罗计算使用MCNP6.2代码与ENDF/B-VIII。0和JEFF-3.3核数据库。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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