METHODS FOR ANALYTICAL AND EXPERIMENTAL JUSTIFICATION OF NUCLEAR AND RADIATION SAFETY DURING UNLOADING AND STORAGE OF SPENT REMOVABLE PARTS FROM NUCLEAR SUBMARINE LIQUID METAL REACTORS

摘要

The analytical and experimental methods applicable for justification of neutronic characteristics of spent removable parts (SRP) of nuclear submarine liquid metal reactors (NS LMR) are briefly reviewed. The following software code systems can be used to justify nuclear and radiation safety, to determine the SNF nuclide composition and energy release: 1. MMKFK-2, based on Monte-Carlo method; 2. «SCALE»; 3. WIMS|ABBN; 4. Updated NucMa version. The methods of determining SRP subcriticality have been developed to experimentally justify nuclear and radiation safety. This paper considers the pulse, stationary and correlation methods of determining NS LMR SRP subcriticality.