Highlights
Purpose and Significance of research focus
Dry cask storage is a method of storing high-level radioactive waste, such as spent nuclear fuel that has already been cooled in the spent fuel pool with an estimation period of 1-10 years. The advantage of dry storage is the passive cooling system and the shielding against radiation emitted from radionuclides. The spent nuclear fuel is increasing in the Nuclear Power Plants (NPPs) and it may exceed the storage capacity of China shortly. So, there is an urgent need to work on the analysis and designing of the advanced storage capacities and equipment for the nuclear fuel management and waste in China. Currently there is no long-term permanent storage facility in China. Dry cask storage is designed as an interim safer solution than spent fuel pool storage. Some of the cask designs can be used for both storage and transportation. This study focuses on preliminary designing of dry storage metallic cask that is neutronics calculation and analyzing defense materials based on their high protective and attenuating properties for its structural modeling or design.
1.2 Research aims and objectives
The aim of the research is a preliminary design and analysis of a dry storage metallic cask in China. It is analyzed the sub-criticality level, and shielding material for the neutronics aspects. This study aimed at proposing an optimized version of the existing German type GNS CASTORV/21 cask model with efficient designs and specifications. The research approach adopted will be through selecting Hualong One Reactor also known as HPR1000, uses a 177-reactor core design in China for neutronics calculation that is modeling the fuel assemblies, cooling period in a pool and finally placing it in a cask for transportation and storage.
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