The worst case scenario including melt-down of reactor core components has been recognized as one of the safety issues. Without any counter measure, this may lead to penetration of RPV (Reactor Pressure Vessel) due to significant thermal loads caused by the relocation of molten core debris into the lower plenum. The present paper shows applicability of ERVC (External Reactor Vessel Cooling), aimed at limiting radiological releases by adopting the in-vessel retention concept, under core melting conditions. Systematic numerical analyses were carried out by taking into account diverse melting progress mechanisms, properties and amounts of molten debris, and damage models. Consequences of the thermal loads under assumed core melting conditions, such as the critical locations and time to reach penetration of the RPV lower plenum, were compared as a part of sensitivity analyses. Also, influences of each parameter were examined and technical findings from the assessment were discussed to demonstrate effectiveness of the ERVC for severe accident mitigation features of new power plants.
Skip Nav Destination
ASME 2013 Pressure Vessels and Piping Conference
July 14–18, 2013
Paris, France
Conference Sponsors:
- Pressure Vessels and Piping Division
- Nondestructive Evaluation Engineering Division
ISBN:
978-0-7918-5569-0
PROCEEDINGS PAPER
Structural Assessment of Reactor Pressure Vessel Under Core Melting Conditions Available to Purchase
Seung-Hyun Kim,
Seung-Hyun Kim
Kyung Hee University, Yongin, Kyonggi, Republic of Korea
Search for other works by this author on:
Yoon-Suk Chang
Yoon-Suk Chang
Kyung Hee University, Yongin, Kyonggi, Republic of Korea
Search for other works by this author on:
Seung-Hyun Kim
Kyung Hee University, Yongin, Kyonggi, Republic of Korea
Yoon-Suk Chang
Kyung Hee University, Yongin, Kyonggi, Republic of Korea
Paper No:
PVP2013-97407, V005T11A015; 5 pages
Published Online:
January 17, 2014
Citation
Kim, S, & Chang, Y. "Structural Assessment of Reactor Pressure Vessel Under Core Melting Conditions." Proceedings of the ASME 2013 Pressure Vessels and Piping Conference. Volume 5: High-Pressure Technology; ASME NDE Division; Rudy Scavuzzo Student Paper Symposium. Paris, France. July 14–18, 2013. V005T11A015. ASME. https://doi.org/10.1115/PVP2013-97407
Download citation file:
16
Views
Related Proceedings Papers
IVR Model Study for Passive PWR
ICONE20-POWER2012
Related Articles
Adaptive Collocation Method for Simultaneous Heat and Mass Diffusion With Phase Change
J. Heat Transfer (August,1984)
The Influence of Crust Layer on Reactor Pressure Vessel Failure Under Pressurized Core Meltdown Accident
ASME J of Nuclear Rad Sci (October,2018)
Development of a New Model of Single-Speed Air Conditioners at Part-Load Conditions for Hourly Simulations
J. Sol. Energy Eng (May,2005)
Related Chapters
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Source Term Assessments in PSA Level 2 for the Outage Period (PSAM-0168)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Summary of Water Hammer-Induced Pipe Failures
Fluid Mechanics, Water Hammer, Dynamic Stresses, and Piping Design