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Iterative Bayesian Monte Carlo for nuclear data evaluation 被引量:7
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作者 Erwin Alhassan Dimitri Rochman +3 位作者 Alexander Vasiliev Mathieu Hursin Arjan JKoning Hakim Ferroukhi 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2022年第4期105-135,共31页
In this work,we explore the use of an iterative Bayesian Monte Carlo(iBMC)method for nuclear data evaluation within a TALYS Evaluated Nuclear Data Library(TENDL)framework.The goal is to probe the model and parameter s... In this work,we explore the use of an iterative Bayesian Monte Carlo(iBMC)method for nuclear data evaluation within a TALYS Evaluated Nuclear Data Library(TENDL)framework.The goal is to probe the model and parameter space of the TALYS code system to find the optimal model and parameter sets that reproduces selected experimental data.The method involves the simultaneous variation of many nuclear reaction models as well as their parameters included in the TALYS code.The‘best’model set with its parameter set was obtained by comparing model calculations with selected experimental data.Three experimental data types were used:(1)reaction cross sections,(2)residual production cross sections,and(3)the elastic angular distributions.To improve our fit to experimental data,we update our‘best’parameter set—the file that maximizes the likelihood function—in an iterative fashion.Convergence was determined by monitoring the evolution of the maximum likelihood estimate(MLE)values and was considered reached when the relative change in the MLE for the last two iterations was within 5%.Once the final‘best’file is identified,we infer parameter uncertainties and covariance information to this file by varying model parameters around this file.In this way,we ensured that the parameter distributions are centered on our evaluation.The proposed method was applied to the evaluation of p+^(59)Co between 1 and 100 MeV.Finally,the adjusted files were compared with experimental data from the EXFOR database as well as with evaluations from the TENDL-2019,JENDL/He-2007 and JENDL-4.0/HE nuclear data libraries. 展开更多
关键词 Iterative Bayesian Monte Carlo(iBMC) Nuclear reaction models Model parameters ADJUSTMENTS Bayesian calibration Nuclear data TALYS
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Bayesian model averaging(BMA)for nuclear data evaluation 被引量:2
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作者 E.Alhassan D.Rochman +1 位作者 G.Schnabel A.J.Koning 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2024年第11期193-218,共26页
To ensure agreement between theoretical calculations and experimental data,parameters to selected nuclear physics models are perturbed and fine-tuned in nuclear data evaluations.This approach assumes that the chosen s... To ensure agreement between theoretical calculations and experimental data,parameters to selected nuclear physics models are perturbed and fine-tuned in nuclear data evaluations.This approach assumes that the chosen set of models accurately represents the‘true’distribution of considered observables.Furthermore,the models are chosen globally,indicating their applicability across the entire energy range of interest.However,this approach overlooks uncertainties inherent in the models themselves.In this work,we propose that instead of selecting globally a winning model set and proceeding with it as if it was the‘true’model set,we,instead,take a weighted average over multiple models within a Bayesian model averaging(BMA)framework,each weighted by its posterior probability.The method involves executing a set of TALYS calculations by randomly varying multiple nuclear physics models and their parameters to yield a vector of calculated observables.Next,computed likelihood function values at each incident energy point were then combined with the prior distributions to obtain updated posterior distributions for selected cross sections and the elastic angular distributions.As the cross sections and elastic angular distributions were updated locally on a per-energy-point basis,the approach typically results in discontinuities or“kinks”in the cross section curves,and these were addressed using spline interpolation.The proposed BMA method was applied to the evaluation of proton-induced reactions on ^(58)Ni between 1 and 100 MeV.The results demonstrated a favorable comparison with experimental data as well as with the TENDL-2023 evaluation. 展开更多
关键词 Bayesian model averaging(BMA) Nuclear data Nuclear reaction models Model parameters TALYS code system Covariances
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Evaluation of neutron cross sections of^(48)Ti based on the Unified-Monte-Carlo-B method
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作者 夏候琼 续瑞瑞 +8 位作者 刘萍 Roberto Capote 田源 陶曦 吴小飞 张玥 葛智刚 舒能川 冯松 《Chinese Physics C》 SCIE CAS CSCD 2024年第7期118-130,共13页
A cross section evaluation of neutron induced reactions on^(48)Ti is undertaken using the Unified Monte Carlo-B(UMC-B)approach.The evaluation concentrates on estimating the covariance and the use of the UMC-B allows a... A cross section evaluation of neutron induced reactions on^(48)Ti is undertaken using the Unified Monte Carlo-B(UMC-B)approach.The evaluation concentrates on estimating the covariance and the use of the UMC-B allows avoiding the deficiencies of linear regression brought by the traditional least squares method.Eight main neutron and charged particle emission reactions from n+^(48)Ti in the fast neutron energy region below 20 MeV are studied in this work.The posterior probability density function(PDF)of each neutron cross section is obtained in a UMC-B Bayesian approach by convoluting the model PDFs sampled based on model parameters and the likelihood functions for the experimental data.Nineteen model parameters including level density,pair corrections,optical model and Kalbach matrix element parameter are stochastically sampled with the assumption of normal distributions to estimate the model uncertainty.The Cholesky factorization approach is applied to consider potential parameter correlations.Finally,the posterior covariance matrices are generated using the UMC-B generated weights.The new evaluated results are compared with the CENDL-3.2,ENDF/B-VIII.0,JEFF-3.3,TENDL-2021 and JENDL-5 evaluations and differences are discussed. 展开更多
关键词 COVARIANCE Unified Monte Carlo B(UMC-B) ^(48)Ti neutron cross sections Cholesky factor-ization approach
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核反应实验数据库(EXFOR) 被引量:5
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作者 王记民 陶曦 +4 位作者 金永利 刘丽乐 陈国长 葛智刚 大塚直彦 《原子核物理评论》 CAS CSCD 北大核心 2021年第1期107-115,共9页
核反应实验数据库(EXFOR)及其检索系统提供了丰富的中低能核反应物理信息和数据,已经成为国际上最全面的核反应实验数据汇编。目前,由国际原子能机构核数据科(IAEA/NDS)协调管理,国际核反应数据中心协作网(NRDC)13个成员进行全球性合作... 核反应实验数据库(EXFOR)及其检索系统提供了丰富的中低能核反应物理信息和数据,已经成为国际上最全面的核反应实验数据汇编。目前,由国际原子能机构核数据科(IAEA/NDS)协调管理,国际核反应数据中心协作网(NRDC)13个成员进行全球性合作,旨在协调国际范围内核反应实验数据的收集、编纂和传播。中国核数据中心(CNDC)作为NRDC成员之一,多年来开展了大量的中子和带电粒子引起的核反应实验测量和建库技术研究。本文介绍了EXFOR数据库的形成、发展和现况,以及数据格式、数据编纂和检索系统,并简要总结了我国核反应实验数据建库及技术研究等方面的工作,如国内期刊检索、EXFOR数据库文档建设、程序开发、国内数据服务及国际合作等。 展开更多
关键词 核反应 实验数据 数据库 EXFOR
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