Covariance comparisons between ENDF/B-VII.1 and ENDF/B-VIII.0 with application for the UAM-LWR exercises
Sign Up to like & getrecommendations! Published in 2020 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2019.107183
Abstract: Abstract In this study, the nuclear-data covariance data have been compared between ENDF/B-VII.1 and ENDF/B-VIII.0. Using NJOY2016.34, the multigroup cross-section covariance libraries based on ENDF/B-VII.1 and ENDF/B-VIII.0 have been generated respectively. From the direct comparisons… read more here.
Keywords: vii endf; endf vii; endf viii; covariance ... See more keywords
Uncertainty comparison between ENDF/B-VIII.0 and ENDF/B-VII.1 for fast reactor BN-600 using high-precision sampling method
Sign Up to like & getrecommendations! Published in 2021 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2021.108457
Abstract: Abstract A method of using small samples to achieve high-precision related variable sequence sampling was proposed. This method mainly uses two techniques: Latin hypercube sampling method for normal distribution and transform the covariance between variables… read more here.
Keywords: high precision; viii endf; endf vii; endf viii ... See more keywords
Sensitivity and uncertainty quantification of neutronic integral data in the TRIGA Mark II research reactor
Sign Up to like & getrecommendations! Published in 2021 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2021.08.003
Abstract: Abstract In order to study the sensitivity and the uncertainty of the Moroccan research reactor TRIGA Mark II, a model of this reactor has been developed in our ERSN laboratory for use with the N-Particle… read more here.
Keywords: uncertainty; research reactor; endf vii; triga mark ... See more keywords
Experimental and simulative studies of thorium fission rates on thorium oxide/depleted uranium cylinders with D-T neutrons
Sign Up to like & getrecommendations! Published in 2017 at "Progress in Nuclear Energy"
DOI: 10.1016/j.pnucene.2017.04.021
Abstract: Abstract Aiming at validating thorium fission parameters and the code used in the conceptual design of fusion-fission hybrid energy reactor, an integral experiment on thorium oxide/depleted uranium cylinder assemblies for thorium fission rate has been… read more here.
Keywords: oxide depleted; fission; endf vii; thorium fission ... See more keywords
A temperature effect analysis of the KRITZ-1 benchmark based on keff decomposition and using the JENDL-4.0 and ENDF/B-VII.1 libraries
Sign Up to like & getrecommendations! Published in 2018 at "Progress in Nuclear Energy"
DOI: 10.1016/j.pnucene.2018.07.012
Abstract: Abstract This paper provides a comparison between multiplication factors within the UO2 fuelled cores that were measured during the original KRITZ-1 experiments performed in the early 1970s. Results were calculated using the MCNP6.1 code and… read more here.
Keywords: temperature; kritz; endf vii; using jendl ... See more keywords
Validation of MVP-II with JENDL-4.0, ENDF/B-VII.1, and JEFF-3.2 through HTC critical experiments
Sign Up to like & getrecommendations! Published in 2019 at "Journal of Nuclear Science and Technology"
DOI: 10.1080/00223131.2019.1610671
Abstract: ABSTRACT In order to validate MVP-II, Haut Taux de Combustion (HTC) experiments were analyzed using a code with relatively new nuclear data libraries, JENDL-4.0, ENDF/B-VII.1, and JEFF-3.2. The effective neutron multiplication factor keff values were… read more here.
Keywords: vii; vii jeff; jendl endf; endf vii ... See more keywords