Neutronic evaluation of transuranics in a GFR model using MCNPX and scale 6.0
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Universidade Federal de Minas Gerais
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In this study, a GFR core model with 100 MWt was evaluated using three different fuel compositions: a
conventional (U, Pu)C and two reprocessed fuels reprocessed by UREX+ technique one spiked with
depleted uranium, (U,TRU)C, and the other one reprocessed spiked with thorium, (Th,TRU)C. The
reprocessed fuel came from a PWR standard fuel (33,000 MWd/T burned) with 3.1% of initial
enrichment and left in the pool by 5 years. Some important nuclides were followed during burnup and kinf
was evaluated for 1400 days. The results also include analysis of the B4C insertion and the temperature
coefficient. The simulations were performed comparing results between MCNPX and SCALE 6.0 codes.
The main goal is to validate the model and evaluate the possibility to use TRU spiked with Th in a GFR.
Abstract
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Urânio, Combustíveis nucleares, Reatores nucleares
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Coefficient of reactivity, Nuclear fuel, Nuclear reactors
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https://inis.iaea.org/records/r9jhr-s3736