EVOL和MARS合作项目框架内的熔盐快堆Neutronic基准

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY
M. Brovchenko, J. Kloosterman, L. Luzzi, E. Merle, D. Heuer, A. Laureau, O. Feynberg, V. Ignatiev, M. Aufiero, A. Cammi, C. Fiorina, F. Alcaro, S. Dulla, P. Ravetto, Lodewijk Frima, D. Lathouwers, B. Merk
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引用次数: 37

摘要

本文介绍了FP7项目EVOL和ROSATOM项目MARS的各个参与者所获得的中子基准和结果。基准测试的目的有两个:首先是验证和验证项目合作伙伴的每个适用于液体燃料反应堆的代码包,其次是检查熔盐快堆(MSFR)应用的堆芯特性对核数据集的依赖性。MSFR在钍燃料循环中运行,可以用233u富集的U和/或TRU元素作为初始裂变负荷。目前的基准涵盖了所有三种组合。计算证实,MSFR具有其他第4代快堆所不具备的非常有利的特性,如强负温度和空性反应系数、低裂变库存、减少长寿命废物产生以及目前运行的反应堆产生的核废料的燃烧能力。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Neutronic benchmark of the molten salt fast reactor in the frame of the EVOL and MARS collaborative projects
This paper describes the neutronic benchmarks and the results obtained by the various participants of the FP7 project EVOL and the ROSATOM project MARS. The aim of the benchmarks was two-fold: first to verify and validate each of the code packages of the project partners, adapted for liquid-fueled reactors, and second to check the dependence of the core characteristics to nuclear data set for application on a molten salt fast reactor (MSFR). The MSFR operates with the thorium fuel cycle and can be started with 233U-enriched U and/or TRU elements as initial fissile load. All three compositions were covered by the present benchmark. The calculations have confirmed that the MSFR has very favorable characteristics not present in other Gen4 fast reactors, like strong negative temperature and void reactivity coefficients, a low-fissile inventory, a reduced long-lived waste production and its burning capacities of nuclear waste produced in currently operational reactors.
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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
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