Abstract
The present SF management concept in Lithuania envisages that spent RBMK-1500 fuel will be stored in dry storage containers for 50 years, before being disposed of in a deep geological repository. However, the risk that a deep geological repository will not be constructed at the planned time should be taken into account, and the extension of SF storage over 50 years should be considered. This paper presents a comparison of gamma and neutron dose rate distributions and variations with planned and extended storage times for cast iron and metal–concrete containers loaded with RBMK-1500 SF. All calculations were performed using the SCALE computer codes system. The modeling results show that the overall shielding properties of the CONSTOR® RBMK-1500 container containing the same neutron and gamma sources are better than those of the CASTOR® RBMK-1500 container. During an extended storage period (from 50 to 300 years), the total dose rate would decrease considerably and the dose rate due to neutrons would become dominant for both containers.
Highlights
The present spent fuel (SF) management concept in Lithuania envisages that spent RBMK-1500 fuel will be stored in dry storage containers for 50 years, before being disposed of in a deep geological repository
The SCALE computer code system is widely used for depletion and decay analysis of RBMK spent fuel [21,22,23,24,25]
We provide a discussion on the energy groups of gamma and neutron emissions from the spent fuel that determine gamma and neutron dose rates on the outer surface of the cast iron and metal–concrete containers for different storage periods; secondly, we present the contributions in percentage of neutrons and gammas to the total dose rate during extended storage times; lastly, we present the total dose rates and their variation with storage time on the side, top, and bottom walls of the cast iron and metal–concrete containers
Summary
The present SF management concept in Lithuania envisages that spent RBMK-1500 fuel will be stored in dry storage containers for 50 years, before being disposed of in a deep geological repository. The risk that a deep geological repository will not be constructed at the planned time should be taken into account, and the extension of SF storage over 50 years should be considered. This paper presents a comparison of gamma and neutron dose rate distributions and variations with planned and extended storage times for cast iron and metal–concrete containers loaded with. Variations with Time for Cast Iron and Metal–Concrete Casks Used for RBMK-1500 Spent Fuel Storage. In the 1990s, most countries canceled their plans for SF reprocessing, but deep geological repositories were not available at that time.
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