THERMAL ANALYSIS OF CASKS FOR INTERIM STORAGE OF RBMK-1500 SPENT NUCLEAR FUEL

Detailed thermal analysis was performed for two types German CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for interim storage of spent nuclear fuel at Ignalina Nuclear Power Plant. Numerical calculation code ALGOR (USA) was used, which allows calculating the temperature and heal flux distributions in fuel assemblies and cask body. The calculations were performed for different cases of single cask or cask in storage facility, when it is just loaded with spent nuclear fuel, and after 50 years of storage, for summer and winter conditions, when the ambient temperatures were accepted 37 and −42°C respectively.