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Jonusan, Raoni A.S.; Pereira, Fernando; Velasquez, Carlos E.; Salome, Jean A.D.; Cardoso, Fabiano; Pereira, Claubia; Fortini, Angela
Associacao Brasileira de Energia Nuclear (ABEN), Rio de Janeiro, RJ (Brazil)2017
Associacao Brasileira de Energia Nuclear (ABEN), Rio de Janeiro, RJ (Brazil)2017
AbstractAbstract
[en] The investigation of the thermal behavior of spent fuel (SF) materials is essential to determining appropriate potential sites to accommodate geological repositories as well as the design of canisters, considering their potential risk to people health and of environmental contamination. This work presents studies of the temperature in a canister containing spent fuels discharged from Pressurized Water Reactor (PWR), Very High-Temperature Reactor (VHTR) and Accelerator-Driven Subcritical Reactor System (ADS) reactor systems in a geological repository concept. The thermal analyses were performed with the software ANSYS, which is widely used to solve engineering problems through the Finite Element Method. The ANSYS Transient Thermal module was used. The spent nuclear fuels were set as heat sources using data of previous studies derived from decay heat curves. The studies were based on comparison of the mean temperature on a canister surface along the time under geological disposal conditions, for a same amount of each type of spent nuclear fuel evaluated. The results conclude that fuels from VHTR and ADS systems are inappropriate to be disposed in a standardized PWR canister, demanding new studies to determine the optimal amount of spent fuel and new internal canister geometries. It is also possible to conclude that the hypothetical situation of a single type of canister being used to accommodate different types of spent nuclear fuels is not technically feasible. (author)
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2017; 10 p; INAC 2017: International Nuclear Atlantic Conference; Belo Horizonte, MG (Brazil); 22-27 Oct 2017
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Miscellaneous
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Conference
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CALCULATION METHODS, ENERGY SOURCES, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, EVALUATION, EXPERIMENTAL REACTORS, FUELS, GAS COOLED REACTORS, GRAPHITE MODERATED REACTORS, HELIUM COOLED REACTORS, HTGR TYPE REACTORS, MATERIALS, MATHEMATICAL SOLUTIONS, NUCLEAR FUELS, NUMERICAL SOLUTION, POWER REACTORS, REACTOR MATERIALS, REACTORS, RESEARCH AND TEST REACTORS, SUBCRITICAL ASSEMBLIES, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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