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Keywords: station blackout
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Proceedings Papers

Shutdown Seal Improvement Feasibility Analysis for CPR1000 Reactor Coolant Pump

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Zhang Hengrui, Huang Qian, Fu Peiren, Zhang Daoke, Cai Rui, Sun Lei, Chen Qiuyang, Xue Feng
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A050, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92727
https://doi.org/10.1115/ICONE29-92727
... the reactor coolant pump seals following a station blackout (SBO) or loss of heat sink accident. After the SBO or loss of heat sink of whole plant occurs, normal main pump shaft seal injection will be lost. The hydrostatic test pump will start automatically to ensure emergency shaft seal injection...
View Paper titled, Shutdown Seal Improvement Feasibility Analysis for CPR1000 Reactor Coolant Pump
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Topics: Damage, Nuclear reactor coolants, Pumps
Proceedings Papers

Investigation of Multifarious Zircaloy-Water Oxidation Models on Core Degadation in a Typical SBO Accident

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Hongping Sun, Yuejian Luo, Jian Deng, Ming Zhang, Xiaoli Wu, Lili Liu, Youyou Xu
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92396
https://doi.org/10.1115/ICONE29-92396
... Power Institute of China, Sichuan, Chengdu, China Youyou Xu Nuclear Power Institute of China, Sichuan, Chengdu, China Keywords: Oxidation models; Core degradation; Station blackout; Hydrogen production. ABSTRACT Cladding oxidation is a particularly important process which can affect the process of core...
View Paper titled, Investigation of Multifarious Zircaloy-Water Oxidation Models on Core Degadation in a Typical SBO Accident
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Topics: Accidents, Hydrogen production, Oxidation, Water
Proceedings Papers

Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor

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R. Lo Frano, S. Paci, P. Darnowski, P. Mazgaj
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A016, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16664
https://doi.org/10.1115/ICONE2020-16664
... in the frame of the EU NARSIS project. A Total Station Blackout (SBO) accident was simulated with MELCOR 2.2 severe accident integral computer code. Results of the analysis, temperatures in the lower head and pressures in the lower plenum were used as initial and boundary conditions for the Finite Element...
View Paper titled, Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor
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Topics: Failure, Finite element methods, Pressurized water reactors, Accidents, Nuclear power stations, Reactor vessels, Boundary-value problems, Computers, Engineering simulation, Materials properties
Proceedings Papers

MELCOR Modeling of Combined Accident Tolerant Fuel and Reactor Core Isolation Cooling System Operation

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Chris Faucett, Bradley Beeny, Karen Vierow Kirkland
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A038, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16409
https://doi.org/10.1115/ICONE2020-16409
... department, a MELCOR BWR model was developed from open source literature. The demonstration shown herein simulates BWR long-term station blackout (LTSBO) conditions with the Nuclear Regulatory Commission’s (NRC) MELCOR severe accident analysis code. By combining state-of-the-art MELCOR modeling practices...
View Paper titled, MELCOR Modeling of Combined Accident Tolerant Fuel and Reactor Core Isolation Cooling System Operation
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Topics: Accidents, Cooling systems, Fuels, Modeling