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- W2565512834 abstract "The classical nuclear fuel UO2 is well known for VVER reactors. Nevertheless, in the near future it will be possible to replace this fuel by novel, advanced kinds of fuel, for instance MOX, inert matrices fuel, etc., that will allow to increase the level of burn-up and minimize the amount of hazardous waste. The code TRANSURANUS [2], designed at ITU Karlsruhe, is intended for thermal and mechanical analyses of fuel elements in nuclear reactors. We have utilized the code TRANSURANUS to simulate the neutron-physical properties of the classical UO2 fuel and of MOX fuel during the burn-up to a level of 40 MWd/kgHM. We compare obtained results of uranium and plutonium nuclides concentrations, their changes during burn-up, with results obtained by code HELIOS [3], which is well-validated code for this kind of applications. We performed calculations of fission gasses concentrations, namely xenon and krypton." @default.
- W2565512834 created "2017-01-06" @default.
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- W2565512834 date "2005-01-01" @default.
- W2565512834 modified "2023-09-27" @default.
- W2565512834 title "Simulation of the Neutron-physical Properties of the Classical UO2 Fuel and of MOX Fuel During the Burn-up by Transuranus" @default.
- W2565512834 hasPublicationYear "2005" @default.
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