Abstract:This paper presents the generation and the verification of the few-group homogenized cross-sections for Batan-Fuel. This code is routinely used for fuel management in the RSG-GAS. The Monte Carlo code Serpent 2 code, in conjunction with the latest nuclear data library ENDF/B-VIII.0, was used. Calculations using the existing newly generated few-group cross-section data were carried out for the 88th core. The calculated core parameters such as excess reactivity and control rod worth are compared to the available… Show more
Set email alert for when this publication receives citations?
scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.