Validation of the MORET 5 Monte Carlo Transport Code on Reactor Physics Experiments
نویسندگان
چکیده
The MORET 5 code, which has been developed over more than 50 years at IRSN, recently evolved, in its continuous energy version, from a criticality oriented code to also focused on reactor physics applications. Some developments such as the implementation of kinetics parameters contribute that evolution. aim paper is present validation for keff multiplication factor used studies well other commonly Special attention will be paid commission tests performed CABRI French Reactor (CABRI pool-type research operated by CEA and located Cadarache site southern France simulate sudden instantaneous increase power, known power transient, typical reactivity-initiated accident (RIA).) IPEN/MB-01 LCT-077 benchmark.
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ژورنال
عنوان ژورنال: Journal of nuclear engineering
سال: 2021
ISSN: ['2673-4362']
DOI: https://doi.org/10.3390/jne2010007