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Comparison of MCNPX-C90 and TRIPOLI-4-D for fuel depletion calculations of a Gas-cooled Fast Reactor |
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| Authors: | Ricardo Reyes-Ramírez Cecilia Martín-del-Campo Juan-Luis François Emeric Brun Eric Dumonteil Fausto Malvagi |
| Affiliation: | 1. Departamento de Sistemas Energéticos, Facultad de Ingeniería, Universidad Nacional Autónoma de México, Paseo Cuauhnáhuac 8532, 62550 Jiutepec, Mor., Mexico;2. CEA Saclay DEN/DM2S/SERMA/LTSD, Bat 470, 91191 Gif-sur-Yvette Cedex, France |
| Abstract: | The Gas-cooled Fast Reactor is one of the reactor concepts selected by the Generation IV International Forum for the next generation of innovative nuclear energy systems. Several fuel design concepts are being investigated. Burnup depletion of mixed fuel of uranium and plutonium, cooled with gas in a fast neutron energy spectrum must be simulated. Various codes are being developed and/or adapted to improve the quality of the results, and also to reduce the computing time required for the simulations. |
| Keywords: | Gas-cooled Fast Reactor MCNPX-C90 TRIPOLI-4-D Fuel depletion calculations |
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