AN ANALYSIS OF SELECTED ATTRIBUTES OF THE SPENT NUCLEAR FUEL VVER-440

Radoslav Zajac - Vladimír Chrapčiak - Vladimír Nečas

   The article presents an analysis of some attributes of spent fuel obtained by the computer code ORIGEN-S in the system SCALE 4.4. Concentrations of selected nuclides, activity, quantity of neutrons and photons, thermal power of a single concrete fuel assembly with enrichment 3.6% for decay times 0.1, 5, 15 years after finishing irradiation for 1, 10 and 1260 calculated points were obtained by ORIGEN-S. The main aim of this study was to estimate the influence of averaging the inputs parameters for the ORIGEN-S. The result tables include actual values and relative deviations.

Keywords: spent nuclear fuel

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