Adjusting JEFF-3.3 actinide data using a new, dedicated methodology for selecting suited assimilation database parameters

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-02-07 DOI:10.1016/j.anucene.2025.111246
Sandro Pelloni, Dimitri Rochman
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Abstract

A general method is proposed to choose, among several benchmarks, suitable assimilation database parameters to be used in adjustments. All these benchmarks are predetermined keeping in mind specific goals of the data assimilation. The main principle of the novel methodology is that of excluding groups of strongly cross-correlated computed parameters by estimating their posterior values of χ2. The assimilation tries minimizing the mean χ2 for the entirety of the considered benchmarks, including those target parameters which are not part of the selected assimilation database.
The methodology currently applied to the JEFF-3.3 library, is demonstrated by adjusting data for 235U, 238U, 239Pu and 240Pu in conjunction with a class of integral parameters (effective multiplication factors) of fast criticalities including the Godiva and Jezebel spheres, for which the effect of varying resonance parameters in the calculations may be largely neglected.
The computed mean χ2 of 36 values in total, among which seven refer to the assimilation database, is halved, and the variance of the individual χ2-values decreases by a factor of 6 with respect to the prior values. More explicitly, the posterior values of respectively 1.10 and 3.77 for χ2 and the variance of the individual χ2-values are much smaller than the corresponding prior values of 2.32 and 22.38, which is significant.
As regards the adjustment, for 235U, it is found that μ¯ and the inelastic scattering cross-section respectively decrease by maximum 3% and 2.6%; ν¯ is uniformly decreased by maximum 0.053% and the fission spectrum is somewhat harder. For 238U, μ¯ increases by maximum 5.4% and the inelastic scattering cross-section is lowered by 1%. For 239Pu, ν¯ is uniformly increased by maximum 0.027% and the fission spectrum is slightly softer. For 240Pu, the fission cross-section is decreased by maximum 3.9%. The proposed adjustments are well within the uncertainty limit of one standard deviation for the nuclear data.
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调整杰夫-3.3锕系数据使用新的,专用的方法来选择合适的同化数据库参数
提出了一种通用的方法,从几个基准中选择合适的同化数据库参数用于调整。所有这些基准都是预先确定的,并牢记数据同化的特定目标。新方法的主要原理是通过估计χ2的后验值来排除强交叉相关计算参数组。同化尝试最小化整个考虑的基准的均值χ2,包括那些不属于所选同化数据库的目标参数。通过对235U、238U、239Pu和240Pu的数据进行调整,并结合Godiva和Jezebel球等一类快速临界积分参数(有效乘法因子),验证了目前应用于JEFF-3.3库的方法,其中不同共振参数在计算中的影响可能在很大程度上被忽略。总共36个值的计算平均值χ2(其中7个引用同化数据库)减半,单个χ2值的方差相对于先前值减小了6倍。更明显的是,χ2的后验值分别为1.10和3.77,个体χ2值的方差远小于相应的前验值2.32和22.38,具有显著性。对于235U, μ¯和非弹性散射截面分别最大减小了3%和2.6%;ν¯均匀地最大减小0.053%,裂变谱稍微硬一些。对于238U, μ¯最大增大5.4%,非弹性散射截面减小1%。对于239Pu, ν¯最大均匀增加0.027%,裂变谱略软。对于240Pu,裂变截面最大减小了3.9%。所建议的调整完全在核数据一个标准差的不确定限度之内。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
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.
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