NUCLEAR TECHNIQUES, Volume. 47, Issue 7, 070601(2024)
Coupled irradiation-thermal-mechanical analysis of fuel in solid core of heat pipe cooled reactor
Fig. 1. Schematic diagram of solid core structure and calculation unit selection
Fig. 2. Coupled irradiation-thermal-mechanical model of solid core
Fig. 3. Boundary condition and numbering setting for coupled irradiation-thermal-mechanical model (a) Boundary condition, (b) Heat pipe and fuel numbering scheme
Fig. 4. Steady-state temperature distribution contour of solid core fuel
Fig. 5. Steady-state stress distribution contour of solid core fuel
Fig. 6. Minimum gap between pellet and cladding (a), between monolith and cladding (b), between monolith and HP (c) varying with running time
Fig. 7. Variation of maximum temperature of pellet with running time
Fig. 8. Creep of monolith and cladding at operation period of 2 000 d (a) Monolith, (b) Monolith and cladding
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Xuan YANG, Quan LI, Chenxi LI, Jing ZHANG, Yingwei WU, Yanan HE, Kailun GUO, Guanghui SU, Wenxi TIAN, Suizheng QIU. Coupled irradiation-thermal-mechanical analysis of fuel in solid core of heat pipe cooled reactor[J]. NUCLEAR TECHNIQUES, 2024, 47(7): 070601
Category: Research Articles
Received: Dec. 28, 2023
Accepted: --
Published Online: Aug. 27, 2024
The Author Email: ZHANG Jing (章静), WU Yingwei (巫英伟)