核数据应用中基于相关采样技术的不确定性传播

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI:10.1051/epjn/2020003
A. Laureau, V. Lamirand, D. Rochman, A. Pautz
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引用次数: 2

摘要

在蒙特卡罗模拟中,采用了一种相关采样技术来估计截面变化对中子输运的影响。这种实现已经与全蒙特卡罗方法相结合,该方法包括用随机截面文件传播核数据的不确定性。TMC-CS (Total Monte Carlo with correlation Sampling)方法提供了相关计算时间的有趣加速。本文详细介绍了该方法,并结合两个应用案例来验证和说明该技术提供的增益:由不锈钢反射器HMI-001基准反射的高浓缩铀/铁金属芯,以及CROCUS零功率轻水反应堆的PETALE实验方案。
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Uncertainty propagation based on correlated sampling technique for nuclear data applications
A correlated sampling technique has been implemented to estimate the impact of cross section modifications on the neutron transport and in Monte Carlo simulations in one single calculation. This implementation has been coupled to a Total Monte Carlo approach which consists in propagating nuclear data uncertainties with random cross section files. The TMC-CS (Total Monte Carlo with Correlated Sampling) approach offers an interesting speed-up of the associated computation time. This methodology is detailed in this paper, together with two application cases to validate and illustrate the gain provided by this technique: the highly enriched uranium/iron metal core reflected by a stainless-steel reflector HMI-001 benchmark, and the PETALE experimental programme in the CROCUS zero-power light water reactor.
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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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