In-Vessel Retention (IVR) of core melt is a key severe accident management strategy adopted by operating nuclear power plants and advanced light water reactors (ALWRs), AP600, AP1000 etc. External Reactor Vessel Cooling (ERVC), which involves flooding the reactor cavity to submerge the reactor vessel in an attempt to cool core debris relocated to the vessel low head, is a novel severe accident management for IVR analysis. In present study, IVR analysis code in severe accident (IVRASA) has been proposed to evaluate the safety margin of IVR in AP600 with anticipative depressurization and reactor cavity flooding in severe accident. For, IVRASA, the point estimate procedure has been developed for modeling the steady-state endpoint of core melt configurations. Furthermore, IVRASA was developed in a more general fashion so that it is applicable to compute various molten configurations such as UCSB FInal Bounding State (FIBS) etc. The results by IVRASA were consistent with those of the UCSB and INEEL. Benchmark calculations of UCSB-assumed FIBS indicate the applicability and accuracy of IVRASA and it could be applied to predict the thermal response of various molten configurations.
Skip Nav Destination
18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4932-3
PROCEEDINGS PAPER
A Novel Point Estimate Procedure for IVR Calculations in Core-Molten Severe Accident
Yapei Zhang,
Yapei Zhang
Xi’an Jiaotong University, Xi’an, China
Search for other works by this author on:
Suizheng Qiu,
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
Search for other works by this author on:
Guanghui Su,
Guanghui Su
Xi’an Jiaotong University, Xi’an, China
Search for other works by this author on:
Wenxi Tian
Wenxi Tian
Xi’an Jiaotong University, Xi’an, China
Search for other works by this author on:
Yapei Zhang
Xi’an Jiaotong University, Xi’an, China
Suizheng Qiu
Xi’an Jiaotong University, Xi’an, China
Guanghui Su
Xi’an Jiaotong University, Xi’an, China
Wenxi Tian
Xi’an Jiaotong University, Xi’an, China
Paper No:
ICONE18-29008, pp. 1-14; 14 pages
Published Online:
April 8, 2011
Citation
Zhang, Y, Qiu, S, Su, G, & Tian, W. "A Novel Point Estimate Procedure for IVR Calculations in Core-Molten Severe Accident." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 1-14. ASME. https://doi.org/10.1115/ICONE18-29008
Download citation file:
13
Views
Related Proceedings Papers
Related Articles
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher
ASME J of Nuclear Rad Sci (October,2019)
Safest Roadmap for Corium Experimental Research in Europe
ASME J. Risk Uncertainty Part B (September,2018)
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)
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Modeling of SAMG Operator Actions in Level 2 PSA (PSAM-0164)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)