A severe accident code was applied for modeling of a typical pressurized water reactor (PWR) nuclear power plant, and the effects of RCS depressurization on the gas temperature of the relief tank cell in the containment during a station blackout (SBO) induced accident was analyzed. The sensitivity calculation indicated that the hydrogen generation rate obviously increased due to RCS depressurization in a critical stage. The results show that RCS depressurization can play an important role in hydrogen generation rate and total accumulation, and the temperature of the containment atmosphere is highly influenced by hydrogen combustion. High temperature induced by hydrogen combustion may degrade the equipment and instruments capabilities. Based on this analysis, a feasible strategy of RCS depressurization for mitigating the accident consequence is provided for developing the capacity of the SBO treatment of Qinshan Phase Nuclear Power Plant (QSP-II NPP).
Skip Nav Destination
2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4593-6
PROCEEDINGS PAPER
Analysis of RCS Depressurization Effects on Containment Temperature for Qinshan Phase II Nuclear Power Plant Available to Purchase
Liu Lili,
Liu Lili
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Zhang Ming,
Zhang Ming
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Deng Jian
Deng Jian
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Liu Lili
Nuclear Power Institute of China, Chengdu, China
Zhang Ming
Nuclear Power Institute of China, Chengdu, China
Deng Jian
Nuclear Power Institute of China, Chengdu, China
Paper No:
ICONE22-30649, V003T06A025; 4 pages
Published Online:
November 17, 2014
Citation
Lili, L, Ming, Z, & Jian, D. "Analysis of RCS Depressurization Effects on Containment Temperature for Qinshan Phase II Nuclear Power Plant." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security. Prague, Czech Republic. July 7–11, 2014. V003T06A025. ASME. https://doi.org/10.1115/ICONE22-30649
Download citation file:
13
Views
Related Proceedings Papers
Related Articles
Fog Inerting Effects on Hydrogen Combustion in a PWR Ice Condenser Containment
J. Heat Transfer (May,1995)
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
In Situ Species Concentration Measurements in Ammonia-Mix Flames Using FTIR Spectroscopy
J. Eng. Gas Turbines Power (July,2025)
Related Chapters
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)
Link between Level 2 PSA and Off-Site Emergency Preparedness (PSAM-0363)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)