It has been identified that the pressure in the reactor coolant system (RCS) remains high in some severe accident sequences at the time of reactor vessel failure, with the risk of causing direct containment heating (DCH). Intentional depressurization is an effective accident management strategy to prevent DCH or to mitigate its effects. Fission product behavior is affected by intentional depressurization, especially for inert gas and volatile fission product. Because the pressurizer power-operated relief valves (PORVs) are latched open, fission product will transport into the containment directly. This may cause larger radiological consequences in containment before reactor vessel failure. Four cases are selected, including the TMLB’ base case and opening one, two and three pressurizer PORVs. The results show that inert gas transports into containment more quickly when opening one and two PORVs, but more slowly when opening three PORVs; more volatile fission product deposit in containment and less in reactor coolant system (RCS) for intentional depressurization cases. When opening one PORV, the phenomena of revaporization is strong in the RCS.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
PROCEEDINGS PAPER
Preliminary Analysis of Effect of the Intentional Depressurization on Fission Product Behavior During TMLB’ Severe Accident
Gaofeng Huang,
Gaofeng Huang
Shanghai Jiaotong University, Shanghai, China
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Lili Tong,
Lili Tong
Shanghai Jiaotong University, Shanghai, China
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Xuewu Cao
Xuewu Cao
Shanghai Jiaotong University, Shanghai, China
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Gaofeng Huang
Shanghai Jiaotong University, Shanghai, China
Lili Tong
Shanghai Jiaotong University, Shanghai, China
Xuewu Cao
Shanghai Jiaotong University, Shanghai, China
Paper No:
ICONE17-75239, pp. 421-425; 5 pages
Published Online:
February 25, 2010
Citation
Huang, G, Tong, L, & Cao, X. "Preliminary Analysis of Effect of the Intentional Depressurization on Fission Product Behavior During TMLB’ Severe Accident." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 421-425. ASME. https://doi.org/10.1115/ICONE17-75239
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