Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2020-04-08 DOI:10.1051/epjn/2020004
A. Laureau, V. Lamirand, D. Rochman, A. Pautz
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引用次数: 2

Abstract

The PETALE experimental programme in the CROCUS reactor intends to provide integral measurements to constrain stainless steel nuclear data. This article presents the tools and the methodology developed to design and optimize the experiments, and its operating principle. Two acceleration techniques have been implemented in the Serpent2 code to perform a Total Monte Carlo uncertainty propagation using variance reduction and correlated sampling technique. Their application to the estimation of the expected reaction rates in dosimeters is also discussed, together with the estimation of the impact of the nuisance parameters of aluminium used in the experiment structures.
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CROCUS反应堆PETALE实验程序设计研究的不确定性传播
CROCUS反应堆中的PETALE实验计划旨在提供积分测量,以约束不锈钢核数据。本文介绍了为设计和优化实验而开发的工具和方法,以及其工作原理。Serpent2代码中已经实现了两种加速技术,以使用方差减少和相关采样技术来执行总蒙特卡罗不确定性传播。还讨论了它们在剂量计中预期反应速率估计中的应用,以及对实验结构中使用的铝的有害参数的影响的估计。
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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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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