Neutronic Performance of the VVER-1000 Reactor Using Thorium Fuel with ENDF Library
نویسندگان
چکیده
In this paper, neutronic calculations and the core analysis of VVER-1000 reactor were performed using MCNP6 code together with both ENDF/B-VII.1 ENDF/B-VIII libraries. The effect thorium introduction on parameters was discussed. reference initially filled enriched uranium oxide fuel then fueled uranium-thorium fuel. determine delayed neutron fraction βeff, temperature reactivity coefficients, consumption, production transuranic elements during operation. βeff Doppler coefficient (DC) are found to be in agreement design values. It is that loaded has lower than core. moderator coefficients higher those Results indicated minor actinides (MAs) (mainly plutonium isotopes) compared relatively large amounts produced from uranium-based UO2.
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ژورنال
عنوان ژورنال: Science and Technology of Nuclear Installations
سال: 2021
ISSN: ['1687-6075', '1687-6083']
DOI: https://doi.org/10.1155/2021/8838097