Criticality Safety Analysis of Spent Fuel Storage Pool for NPP Mochovce using MCNP5 Code
نویسندگان
چکیده
The paper presents results of nuclear criticality safety analysis spent fuel storage and handling for the 1st 2nd unit NPP Mochovce. Spent pool (compact reserve grid) T-12 transport cask were modeled using Monte Carlo code MCNP5. Conservative approach was applied calculation max eff k values performed normal various postulated emergency conditions in order to evaluate final maximal values. requirement current regulations ensure 5% subcriticality met except some especially conservative cases.
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ژورنال
عنوان ژورنال: Energija
سال: 2022
ISSN: ['0354-8651', '2812-7528']
DOI: https://doi.org/10.37798/2013621-4226