Martin Skretteberg, Paul Cosgrove, Mikolaj Kowalski
{"title":"A non-parametric bootstrap method for Monte Carlo neutron transport","authors":"Martin Skretteberg, Paul Cosgrove, Mikolaj Kowalski","doi":"10.1016/j.anucene.2024.111168","DOIUrl":null,"url":null,"abstract":"<div><div>A new variability inference technique for Monte Carlo transport methods has been investigated. This approach is based on non-parametric bootstrapping, a statistical inference and resampling method in which an observed set of samples is used to generate simulated samples to infer statistical properties of the underlying distribution from which the original samples were drawn. In this way, non-parametric bootstrapping can be applied to estimators to quantify the uncertainty of the corresponding estimates as well as any bias introduced by bootstrapping, which can then be used to correct the bias. In this context, we have used non-parametric bootstrapping to estimate the first and second-order moments of estimations of Monte Carlo integral responses for different neutron transport problems. This was implemented in SCONE — Stochastic Calculator Of Neutron transport Equation, developed at the University of Cambridge. Results show that the non-parametric bootstrap method can improve the efficiency of the estimates, that is, achieve a favourable trade-off between simulation time and variance of integral response estimates while being more accurate, compared to standard MC estimates. This is particularly the case for low sample sizes and when the number of responses is kept to a moderate level, which is expected according to the underlying theory which has been investigated. As the number of responses increases, however, challenges with bias, memory and computational efficiency become more prominent, which is addressed.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"213 ","pages":"Article 111168"},"PeriodicalIF":1.9000,"publicationDate":"2024-12-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454924008314","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
Abstract
A new variability inference technique for Monte Carlo transport methods has been investigated. This approach is based on non-parametric bootstrapping, a statistical inference and resampling method in which an observed set of samples is used to generate simulated samples to infer statistical properties of the underlying distribution from which the original samples were drawn. In this way, non-parametric bootstrapping can be applied to estimators to quantify the uncertainty of the corresponding estimates as well as any bias introduced by bootstrapping, which can then be used to correct the bias. In this context, we have used non-parametric bootstrapping to estimate the first and second-order moments of estimations of Monte Carlo integral responses for different neutron transport problems. This was implemented in SCONE — Stochastic Calculator Of Neutron transport Equation, developed at the University of Cambridge. Results show that the non-parametric bootstrap method can improve the efficiency of the estimates, that is, achieve a favourable trade-off between simulation time and variance of integral response estimates while being more accurate, compared to standard MC estimates. This is particularly the case for low sample sizes and when the number of responses is kept to a moderate level, which is expected according to the underlying theory which has been investigated. As the number of responses increases, however, challenges with bias, memory and computational efficiency become more prominent, which is addressed.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.