NUCLEAR TECHNIQUES, Volume. 47, Issue 9, 090602(2024)
Development and validation of a thermal-hydraulic analysis code for dual cooled assemblies in molten salt reactors
Fig. 1. Hollow hexagonal assembly (a) and dual cooled assembly (b)
Fig. 2. Actual model (a) and equivalent model (b) of the dual cooled assembly
Fig. 3. Axial normalized power distribution of fuel salt and graphite
Fig. 4. Schematic of heat transfer in a dual cooled component (a) Dual cooling, (b) External channel fuel salt heating graphite, (c) Inner channel fuel salt heating graphite (color online)
Fig. 8. Molten salt temperature distribution of the internal and external channel
Fig. 9. Curves of maximum outlet temperature of fuel salt varying with the level of various factors
Fig. 10. (a) Temperature distribution at the hottest section of graphite, (b) graphite normalized radial temperature distribution of the CFD model
Fig. 11. Graphite normalized radial temperature distribution on the hottest section
Fig. 12. Maximum temperature of graphite varying with the level of each factor
Fig. 13. (a) Molten salt temperature distribution, (b) graphite normalized radial temperature distribution
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Siqin HU, Chong ZHOU, Guifeng ZHU, Yang ZOU, Xiaohan YU, Shuaiyu XUE. Development and validation of a thermal-hydraulic analysis code for dual cooled assemblies in molten salt reactors[J]. NUCLEAR TECHNIQUES, 2024, 47(9): 090602
Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING
Received: Nov. 16, 2023
Accepted: --
Published Online: Nov. 13, 2024
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