ABSTRACT: Evaluated Nuclear Data Files (ENDF) can be used for neutronic analysis of thermal reactor such as research reactor. JENDL-4.0u (Japanese Evaluated Nuclear Data Library) is released by JAEA to read in
ENDF-6 format. The aim of this analysis is to validate the nuclear data files of JENDL-4.0u for neutronics
calculation of 3-MW TRIGA MARK-II research reactor through the analysis of integral parameters of TRX (Thermal Reactor-one region lattice) and BAPL (Bettis Atomic Power Laboratory-one region lattice) benchmark lattices of thermal reactor..............
Keywords: BAPL, JENDL-4.0u, NJOY99.0, TRIGA MARK-II, TRX and WIMSD-5B
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