Radiation and Nuclear Safety Analysis for the Spent Fuel Transportation Package After the Short-Term Cooling by Using Computer Simulation Modeling Methods

The paper presents the results of studies to substantiate the possibility of using a transport container for the spent nuclear fuel after short-term cooling. Calculations for radiation protection have been completed, nuclear safety has been justified, and the relevant accompanying neutron-physical processes have been studied. As a result, technical feasibility of using a transport container for spent nuclear fuel has been substantiated. The most acceptable option of a container for spent nuclear fuel is to be made of iron-concrete + uranium dioxide and cast iron + uranium dioxide with gas filling or with liquid filling of the absorber in a basket. To achieve the set goal, methods of computer simulation modeling were used, calculations were conducted to justify radiation protection and nuclear safety under normal and emergency operating conditions, and neutron-physical processes accompanying spent nuclear fuel were studied. The work examined several options for materials for radiation protection, depending on their thickness and the fill of the spent nuclear fuel container.