TRANSURANUS VERSUS HELIOS: COMPUTATION OF SELECTED NUCLIDES IN BURNT-UP NUCLEAR FUEL

Juraj Breza, Jr. – Vladimír Šebian – Vladimír Nečas

   Computer codes TRANSURANUS and HELIOS are used to compute the concentrations of nuclides in the classical UO₂ nuclear fuel and in the mixed oxide fuel (MOX) during the burn-up. The results are critically discussed.

Keywords: nuclear fuel, burn-up, uranium, plutonium, TRANSURANUS, HELIOS

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