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All issues EPJ Nuclear Sci. Technol., 4 (2018) 7 Article references

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Cited article:

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Neutron-induced damage simulations: Beyond defect production cross-section, displacement per atom and iron-based metrics

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Preliminary Assessment of Criticality Safety Constraints for Swiss Spent Nuclear Fuel Loading in Disposal Canisters

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Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor

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TENDL: Complete Nuclear Data Library for Innovative Nuclear Science and Technology

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Examples of Monte Carlo techniques applied for nuclear data uncertainty propagation

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EPJ Web of Conferences 211 07008 (2019)
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Cross-observables and cross-isotopes correlations in nuclear data from integral constraints

Eric Bauge, Dimitri A. Rochman and Cyrille de Saint Jean
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Efficient use of Monte Carlo: the fast correlation coefficient

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