In the core meltdown severe accident, in-vessel retention (IVR) of molten core debris by external reactor vessel cooling (ERVC) is an important mitigation strategy. During the IVR strategy, the core debris forming a melt pool in the reactor pressure vessel (RPV) lower head (LH) will produce extremely high thermal and mechanical loadings to the RPV, which may cause the failure of RPV due to over-deformation of plasticity or creep. Therefore, it is necessary to study the thermomechanical behavior of the reactor vessel LH during IVR condition. In this paper, under the assumption of IVR-ERVC, the thermal and structural analysis for the RPV lower head is completed by finite element method. The temperature field and stress field of the RPV wall, and the plastic deformation and creep deformation of the lower head are obtained by calculation. Plasticity and creep failure analysis is conducted as well. Results show that under the assumed conditions, the head will not fail due to excessive creep deformation within 200 hours. The results can provide basis for structural integrity analysis of pressure vessels.
Skip Nav Destination
ASME 2018 Pressure Vessels and Piping Conference
July 15–20, 2018
Prague, Czech Republic
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5163-0
PROCEEDINGS PAPER
Thermal and Structural Analysis of Reactor Vessel Lower Head Considering Core Meltdown Accident
Juan Luo,
Juan Luo
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Jiacheng Luo,
Jiacheng Luo
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Lei Sun,
Lei Sun
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Peng Tang
Peng Tang
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Juan Luo
Nuclear Power Institute of China, Chengdu, China
Jiacheng Luo
Nuclear Power Institute of China, Chengdu, China
Lei Sun
Nuclear Power Institute of China, Chengdu, China
Peng Tang
Nuclear Power Institute of China, Chengdu, China
Paper No:
PVP2018-85101, V03BT03A055; 6 pages
Published Online:
October 26, 2018
Citation
Luo, J, Luo, J, Sun, L, & Tang, P. "Thermal and Structural Analysis of Reactor Vessel Lower Head Considering Core Meltdown Accident." Proceedings of the ASME 2018 Pressure Vessels and Piping Conference. Volume 3B: Design and Analysis. Prague, Czech Republic. July 15–20, 2018. V03BT03A055. ASME. https://doi.org/10.1115/PVP2018-85101
Download citation file:
29
Views
Related Proceedings Papers
Related Articles
Deformation and Life Estimates for a Metal Matrix—Spherical Particulate Subjected to Thermomechanical Loading
J. Eng. Mater. Technol (July,2006)
Applications of Energy Release Rate Techniques to Part-Through Cracks in Experimental Pressure Vessels
J. Pressure Vessel Technol (November,1982)
Elastic-Plastic Analysis of the Maximum Postulated Flaw in the Beltline Region of a Reactor Vessel
J. Pressure Vessel Technol (November,1982)
Related Chapters
Basic Concepts
Design & Analysis of ASME Boiler and Pressure Vessel Components in the Creep Range
Microstructure Evolution and Physics-Based Modeling
Ultrasonic Welding of Lithium-Ion Batteries
Basic Concepts
Analysis of ASME Boiler, Pressure Vessel, and Nuclear Components in the Creep Range