钠快堆中子屏蔽中子计算的混合方法

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2021-01-01 DOI:10.1051/epjn/2021016
Amine Hajji, C. Coquelet-Pascal, P. Blaise
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引用次数: 0

摘要

快中子反应堆中子屏蔽中的中子计算是一个复杂的问题,确定性格式通常不适合此类计算,而由于中子屏蔽中的通量水平非常低,蒙特卡罗编码的计算性能很差。本文对这两种方法进行了研究,并对ASTRID快堆基准中子屏蔽的混合方案进行了研究。该混合方案采用确定性码计算的裂变源,利用方差约简技术用蒙特卡罗码精确计算屏蔽层中的中子通量。这为验证确定性计算提供了参考结果。在确定性代码和这种混合参考之间的比较表明,获得了很大的偏差,高达50%。进一步的研究表明,需要处理的物理现象包括高能散射规律的各向异性和碳化硼屏蔽层内部的空间自屏蔽。这些改进将偏差降低到10%以下。最后介绍了中子屏蔽设计准则的一些应用,如中子屏蔽的产气量和中间换热器二次钠的活化。
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A hybrid approach for neutronics calculations in the neutron shielding of sodium fast reactors
Neutron calculations in the neutron shielding of fast neutron reactors are a complex problem as deterministic schemes are usually not suited for such calculations while Monte-Carlo codes have poor computational performance due to the very low flux levels in neutron shields. In this article, both methods are studied, as well as a hybrid scheme on the neutron shielding of the ASTRID fast reactor benchmark. This hybrid scheme uses a fission source calculated by a deterministic code in order to precisely calculate neutron fluxes in the shielding with a Monte-Carlo code using variance reduction techniques. This provides reference results in order to validate deterministic calculations. Comparisons between deterministic codes and this hybrid reference show that large biases are obtained, up to 50%. Further studies are made to reduce the biases, showing that many physical phenomena should be treated, including anisotropy of the scattering law at high energies and spatial self-shielding inside the boron carbide shielding. These improvements reduce the biases to less than 10%. Finally, some applications to designing criteria for the neutron shielding are presented, such as gas production in the neutron shielding and activation of secondary sodium at the intermediate heat exchanger (IHX).
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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
期刊最新文献
Technical note: stable and unstable reactors Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables Templates of expected measurement uncertainties for (n, xn) cross sections Templates of expected measurement uncertainties for total neutron cross-section observables Templates of expected measurement uncertainties for prompt fission neutron spectra
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