Assessment of the core-catcher in the VVER-1000 reactor containment under various severe accidents
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The core catcher is used as a passive safety system in new generation nuclear power plants to create a space in the containment for the placing and cooling of the molten corium under various severe accidents. This research investigates the role of the core catcher in the VVER-1000 reactor containment system in mitigating the effects of core meltdown under various severe accidents within the context of the Ex-vessel Melt Retention (EVMR) strategy. Hence, a comparison study of three severe accidents is conducted, including Station Black-Out (SBO), SBO combined with the Large Break Loss of Coolant Accident (LB-LOCA), and SBO combined with the Small Break Loss of Coolant Accident (SB-LOCA). Numerical comparative simulations are performed for the aforementioned scenario with and without the EX-vessel core-catcher. The results showed that considering the EX-Vessel core catcher reduces the amount of hydrogen by about 18.2 percent in the case of SBO þ LB-LOCA, and hydrogen production decreases by 12.4 percent in the case of SBO þ SB-LOCA. Furthermore, in the presence of an EX-Vessel core-catcher, the production of gases such as CO and CO2 for the SBO accident is negligible. It was revealed that the greatest decrease in pressure and temperature of the containment is related to the SBO accident.
Abstract
The core catcher is used as a passive safety system in new generation nuclear power plants to create a space in the containment for the placing and cooling of the molten corium under various severe accidents. This research investigates the role of the core catcher in the VVER-1000 reactor containment system in mitigating the effects of core meltdown under various severe accidents within the context of the Ex-vessel Melt Retention (EVMR) strategy. Hence, a comparison study of three severe accidents is conducted, including Station Black-Out (SBO), SBO combined with the Large Break Loss of Coolant Accident (LB-LOCA), and SBO combined with the Small Break Loss of Coolant Accident (SB-LOCA). Numerical comparative simulations are performed for the aforementioned scenario with and without the EX-vessel core-catcher. The results showed that considering the EX-Vessel core catcher reduces the amount of hydrogen by about 18.2 percent in the case of SBO þ LB-LOCA, and hydrogen production decreases by 12.4 percent in the case of SBO þ SB-LOCA. Furthermore, in the presence of an EX-Vessel core-catcher, the production of gases such as CO and CO2 for the SBO accident is negligible. It was revealed that the greatest decrease in pressure and temperature of the containment is related to the SBO accident.
참고문헌 (22)
- Y. Maruyama, "A study on concrete degradation during molten core", concrete interactions, 2006, pp.236, 2237~2244
- 이호재, "Assessment of Mass Fraction and Melting Temperature for the Application of Limestone Concrete and Siliceous Concrete to Nuclear Reactor Basemat Considering Molten Coree-Concrete Interaction", Nuclear Engineering and Technology, 48(2), pp.448~456 (2016), 한국원자력학회
- T. Huong Vo, "An analysis of containment responses during a station blackout accident", J. Nucl. Sci. Technol, 54(10), pp.1074~1084 (2017)
- B. D. Boeck, "Prevention and mitigation measures to ensure containment integrity", Nucl. Eng. Des, 209, pp.147~154 (2001)
- N. Muellner, "Investigation of H2 generation during a SBO for a VVER 1000", v320 using the codes RELAP5-SCDAP and MELCOR, 2004, ~
- K. O. Noori, "Analysis of thermalehydraulic parameters of WWER-1000 containment in a large break LOCA", Ann. Nuc. Energy, 68, pp.101~111 (2014)
- Mehdi Dehjourian, "Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor", Nuclear Engineering and Technology, 48(5), pp.1174~1183 (2016), 한국원자력학회
- R. Gharari, "Study the effects of various parameters on hydrogen production in the WWER1000", V446, 2020, pp.124, 103~370
- M. Salehi, "Investigation of LB-LOCA in VVER-1000 NPP using RELAP5", SCDAP and CONTAIN codes, 2020, pp.139, 107229~
- B. Lin, "Development and verification of molten corium concrete interaction code", Prog. Nucl. Energy, 85, pp.701~706 (2015)
- P. Chai, "Numerical simulation of MCCI based on MPS method with different types of concrete", Ann. Nucl. Energy, 103, pp.227~237 (2017)
- S. V. Svetlov, "Core-catcher for tianwan NPP with VVER-1000 reactor", Concept, Design and Justification. 11th Int. Conference on Nucl. Eng (2003)
- Yu. A. Zvonarev, "Numerical Analysis of core-catcher efficiency for VVER-1200", Phys. At. Nuclei, 74, pp.1845~1853 (2011)
- A. A. Sulatsky, "Molten corium interaction with oxidic sacrificial material of VVER core-catcher", Proceedings of ICAPP ’05 Seoul, pp.5240~ (2005)
- VLADIMIR BENZIANOVICH KHABENSKY, "SEVERE ACCIDENT MANAGEMENT CONCEPT OF THE VVER-1000 AND THE JUSTIFICATION OF CORIUM RETENTION IN A CRUCIBLE-TYPE CORE CATCHER", Nuclear Engineering and Technology, 41(5), pp.561~574 (2009), 한국원자력학회
- M. Fischer, "Mitigation of severe accidents in AREVA's Gen 3þ nuclear power plants", Nucl. Eng. Des, 269, pp.323~329 (2014)
- Y. Zvonarev, "The Strategy of Melt Localization for VVER Reactors under Severe Accidents", The 9TH European Review Meeting on Severe Accident Research, ERMSAR2019 (2019)
- Final Safety Analysis Report (FSAR)for Bushehr VVER-1000 Reactor, "Atomic Energy Organization of Iran", ~ (2003)
- R. O. Gauntt, "MELCOR computer code manuals, Primer and Users’ Guide 1(2005) 6, Version 1.8", ~ (2005)
- Final Safety Analysis Report (FSAR)for Bushehr VVER-1000 Reactor, "Atomic Energy Organization of Iran", ~ (2005)
- W. Ma, "In-vessel melt retention of pressurized water reactors: historical review and future research needs", Engineering, 2, pp.103~111 (2016)
- F. Salari, "Investigation of ex-vessel core-catcher for SBO accident in VVER-1000", V528 containment using MELCOR code, 2021, pp.32, 43~