2026-10-06T17:02:14Z https://www.scidb.cn/oai

10.57760/sciencedb.38246 2026-08-20T17:02:59Z

2026-08-20 The data of the article “Quantification of Nuclear Data Uncertainty Propagation in CEFR Using New Mainstream Evaluation Libraries" doi:10.57760/sciencedb.38246 en The dataset was generated through the following four steps. First, nuclear data covariance matrices were produced from the evaluated nuclear data libraries ENDF/B‑VIII.1, JEFF‑3.3, JENDL‑5.0, and TENDL‑2023 using the nuclear data processing code NJOY2016. Second, the sensitivity coefficients of keff and βeff with respect to nuclear data were calculated by a Monte Carlo program combined with the first‑order perturbation method with adjoint weighting. Third, the nuclear‑data‑induced uncertainties in keff and βeff were quantified by combining the covariance matrices with the sensitivity coefficients. Finally, the energy‑dependent uncertainty contribution factor method was applied to identify and rank the contributions of nuclear data in specific energy ranges to the total uncertainties of keff and βeff, thereby clarifying the main sources of uncertainty.All data used in this paper are saved in Origin format and can be opened with Origin2021. The correspondences between the data files and the figures in the text are as follows:(1) The file “不同评价库中铀-238非弹性散射截面不确定度” contains the uncertainty data of the inelastic scattering cross section of uranium‑238 from the ENDF/B‑VIII.1, JEFF‑3.3, and JENDL‑5.0 libraries, corresponding to Figure 1.(2) The file “keff不确定性主要来源” provides the main sources of keff uncertainty under different evaluated libraries and a comparison of the contribution differences among the libraries, corresponding to Figure 5.(3) The file “keff对核数据的敏感性系数” gives the sensitivity coefficients of keff to 33‑group nuclear data, corresponding to Figure 6.(4) The files “235U-fission-ENDF-B-VIII.1 协方差”, “235U-fission-JEFF-3.3-协方差”, “235U-fission-JENDL-5.0协方差”, and “235U-fission-TENDL-2023-协方差” provide the covariance matrix data of the uranium‑235 fission cross section from the ENDF/B‑VIII.1, JEFF‑3.3, JENDL‑5.0, and TENDL‑2023 libraries, respectively, corresponding to Figure 7.(5) The files “ENDF-B-VIII.1中铀-235裂变截面对keff不确定度的贡献分布” and “JEFF-3.3中铀-235裂变截面对keff不确定度的贡献分布” give the contribution distributions of the uranium‑235 fission cross section to keff uncertainty from the ENDF/B‑VIII.1 and JEFF‑3.3 libraries, respectively, corresponding to Figure 8.(6) The file “βeff不确定性主要来源” provides the main sources of βeff uncertainty under different evaluated libraries and a comparison of the contribution differences among the libraries, corresponding to Figure 9.(7) The file “βeff对核数据的敏感性系数” gives the sensitivity coefficients of βeff to 33‑group nuclear data, corresponding to Figure 10.(8) The files “ENDF-B-VIII.1中铀-235缓发裂变中子数多群协方差” and “JENDL-5.0中铀-235缓发裂变中子数多群协方差” provide the 33‑group covariance data of the delayed fission neutron number of uranium‑235 from the ENDF/B‑VIII.1 and JENDL‑5.0 libraries, respectively, corresponding to Figure 11.(9) The files “ENDF-B-VIII.1中铀-235缓发裂变中子数对βeff不确定度的贡献分布” and “JENDL-5.0中铀-235缓发裂变中子数对βeff不确定度的贡献分布” give the contribution distributions of the delayed fission neutron number of uranium‑235 to βeff uncertainty from the ENDF/B‑VIII.1 and JENDL‑5.0 libraries, respectively, corresponding to Figure 12.The above submitted files cover all the core data that support the findings of this paper. nuclear data; sensitivity analysis; uncertainty quantification Chao Yang PUBLIC https://creativecommons.org/licenses/by-nc-nd/4.0/ dataset http://www.doi.org/10.7498/aps.75.20260757 Science Data Bank