The TENDL library is now established as one of the major nuclear data libraries in the world,
striving for completeness and quality of nuclear data files for all isotopes, evaluation …

The impact of the current nuclear data library covariances such as in ENDF/B-VII. 1, JEFF-
3.2, JENDL-4.0, SCALE and TENDL, for relevant current reactors is presented in this work …

In this study, an analysis on burnup credit for cask criticality safety in BWR spent fuel is
conducted. Accurate burnup credit can be used to reduce overly conservative safety margins …

Abstract Characterization of the energy released from radionuclide decay in nuclear fuel
discharged from reactors is essential for the design, safety, and licensing analyses of used …

The bias and uncertainty of calculated decay heat from spent nuclear fuel (SNF) are
essential for code validation. Also, predicting these quantities is crucial for deriving decay …

Abstract The use of Monte-Carlo (MC) simulations for neutronic reactor core physics has
been of high interest since long. Resulting MC models would be relevant, eg, for high …

Decay heat residuals of spent nuclear fuel (SNF), ie, the differences between calculations
and measurements, were obtained previously for various spent fuel assemblies (SFA) using …

Uncertainty quantification (UQ) of spent nuclear fuel (SNF) is a crucial task that provides
predictions and confidence bounds for important quantities of interest, such as decay heat …

Приводится краткое описание функциональных возможностей про граммного
комплекса оптимизации параметров нейтронно физических моделей (нейтронные …

The covariance matrices for the evaluated resolved resonance region parameters are
typically processed into a grouped covariance representation for use in uncertainty …