Аннотация
The paper presents the results of studies to substantiate the possibility of using a container for transfer of spent nuclear fuel after the short-term cooling. Spent nuclear fuel source-terms and energy release calculations, as well as thermal hydraulic calculations have been made to serve as the basis for further studies. The proposed transport package is designed for transportation of recently discharged spent nuclear fuel with a high level of radioactivity. It is assumed that the use of this package allow transportation of up to 5 fuel assemblies from high-power reactors such as ABWR, AP1000, and VVER-1000. As a result of this study, the possibility of using a transport package for spent fuel assemblies after the short-term cooling is substantiated in terms of the thermal processes that occur within them. These processes impose specific restrictions on the container design. This work is the first part of a comprehensive study aimed to substantiate the possibility of transporting spent fuel after the short-term cooling and develop requirements for the design of such transport packages.