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Cited article:

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EXFOR utility codes (ForEXy) and their application to neutron fission cross section evaluation

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Applied Radiation and Isotopes 225 111903 (2025)
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EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5

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Journal of Nuclear Science and Technology 59 (8) 1004 (2022)
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Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances

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Progress in Nuclear Energy 96 76 (2017)
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Incorporating Experimental Information in the Total Monte Carlo Methodology Using File Weights

P. Helgesson, H. Sjöstrand, A.J. Koning, et al.
Nuclear Data Sheets 123 214 (2015)
https://doi.org/10.1016/j.nds.2014.12.037