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Keywords: Containment spray
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Proceedings Papers
Research on Diffusion and Mitigation of Severe Accident Source Terms in Floating Nuclear Power Plant
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-139205
.... The accident process, release and migration of the source terms after the accident are studied. At the same time, the mitigation effect of containment spray on severe accident source terms is studied, as well. The results show that after the accident, the total amount of noble gases is about 99.7...
Proceedings Papers
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92721
...Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92721 DEVELOPMENT OF CONTAINMENT SPRAY REMOVAL MODEL FOR INTEGRATED SEVERE ACCIDENT ANALYSIS CODE ISAA Jishen Li School of Nuclear Science and Technology, Xi an Jiaotong...
Proceedings Papers
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, V001T01A007, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16311
... Abstract After the loss of coolant accident (LOCA), the safety injection system injects water into the reactor coolant system (RCS), and the residual heat rejects from the break. The containment spray system is operating in recirculating cooling mode to ensure that the containment is cooldown...
Proceedings Papers
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, V001T01A008, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16312
... Abstract Large break LOCA will cause an increase in containment pressure, containment temperature and containment radiation level in nuclear power plants (NPPs). Containment spray is one of the most effective ways to mitigate the consequences of large break LOCA for these following facts, first...
Proceedings Papers
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 835-843, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22637
... Local hydrogen behaviors Containment spray Subcompartment NPP Severe accident During severe accidents in nuclear power plant (NPP), the limit of local hydrogen concentration is regulated to ensure the integrity of containment. In this study hydrogen mixing experiments were conducted...