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Proceedings Papers

Research on Martensitic Stainless Steel Used on the Latch Housing of European Pressurized Reactor (EPR) Control Rod Drive Mechanism (CRDM)

Cuizhu He, Yinhui Lan
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A018, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91786
https://doi.org/10.1115/ICONE29-91786
View Paper titled, Research on Martensitic Stainless Steel Used on the Latch Housing of European Pressurized Reactor (EPR) Control Rod Drive Mechanism (CRDM)
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Topics: European pressurized reactors, Manufacturing, Pressure, Stainless steel
Proceedings Papers

AFCEN RCC-F: A New Standard for the Fire Protection Design of New Built Light Water Nuclear Power Plants

Bernard Gautier, Mickael Cesbron, Richard Tulinski
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81893
https://doi.org/10.1115/ICONE26-81893
View Paper titled, AFCEN RCC-F: A New Standard for the Fire Protection Design of New Built Light Water Nuclear Power Plants
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Topics: Design, Fire, Nuclear power stations, Water, Pressurized water reactors, Hazards, Regulations, Safety, China, Construction
Proceedings Papers

EPR: Burnable Absorber Optimization

Michal Zeman, Radek Škoda, Jiří Závorka
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81215
https://doi.org/10.1115/ICONE26-81215
View Paper titled, EPR: Burnable Absorber Optimization
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Topics: Optimization, Fuels, European pressurized reactors, Nuclear fuel cycle, Nuclear fuels
Proceedings Papers

Qualification of Ultrasonic Examination for RPV Nozzle to Shell Welds of EPR Nuclear Power Plant

WeiQiang Wang, Zhe Yu, Xin Ye, HuaiDong Chen, GuanBing Ma
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A098, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67433
https://doi.org/10.1115/ICONE25-67433
View Paper titled, Qualification of Ultrasonic Examination for RPV Nozzle to Shell Welds of EPR Nuclear Power Plant
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Topics: Nozzles, Nuclear power stations, Shells, Ultrasonic testing, Welded joints, Reactor vessels, China, Circuits, Construction, European pressurized reactors
Proceedings Papers

Performances Analyses of Crud of EPR Fuel Assembly

Xuming Wang, Cenxi Yuan, Chen Ye
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A007, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66204
https://doi.org/10.1115/ICONE25-66204
View Paper titled, Performances Analyses of Crud of EPR Fuel Assembly
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Topics: Fuels, Manufacturing, Risk assessment, Boron, Pressurized water reactors, Risk, Cladding systems (Building), Corrosion, Electricity (Physics), European pressurized reactors
Proceedings Papers

Validation and Benchmarking of Comprehensive Vibration Assessment Program for Prototype Reactor Internals

Jianfeng Yang, Lixin Yu, Byounghoan Choi
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 205-209, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55217
https://doi.org/10.1115/ICONE20-POWER2012-55217
View Paper titled, Validation and Benchmarking of Comprehensive Vibration Assessment Program for Prototype Reactor Internals
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Topics: Engineering prototypes, Vibration, Boiling water reactors, Pressurized water reactors, Design, Nuclear power stations, Errors, European pressurized reactors, Failure, Fatigue analysis
Proceedings Papers

EDF’s Engineering Experience and Contribution to the Nuclear Development

Bernard Salha, Bernard Fourest, Jean-Marc Arpino
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 2, 525-529, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22116
https://doi.org/10.1115/ICONE10-22116
View Paper titled, EDF’s Engineering Experience and Contribution to the Nuclear Development
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Topics: China, Design, Energy policy, European pressurized reactors, Feedback, Life extension, Nuclear industry, Nuclear power, Nuclear power stations, Optimization
Proceedings Papers

Physics of Plutonium and Americium Recycling in PWR Using Advanced Fuel Concepts

E. Hourcade
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 897-904, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49604
https://doi.org/10.1115/ICONE12-49604
View Paper titled, Physics of Plutonium and Americium Recycling in PWR Using Advanced Fuel Concepts
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Topics: Fuels, Physics, Pressurized water reactors, Recycling, Manufacturing, Fuel rods, Storage, Cooling systems, Cycles, European pressurized reactors
Proceedings Papers

The Core Melt Stabilization Concept of the EPR and Its Experimental Validation

Manfred Fischer
Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 25-34, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89088
https://doi.org/10.1115/ICONE14-89088
View Paper titled, The Core Melt Stabilization Concept of the EPR and Its Experimental Validation
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Topics: Accidents, Boiling, Concretes, Containment, Cooling, Defense industry, Design, European pressurized reactors, Explosions, Failure
Proceedings Papers

The Development of Severe Accident Codes at IRSN and Their Application to Support the Safety Assessment of EPR

Cataldo Caroli, Alexandre Bleyer, Ahmed Bentaib, Patrick Chatelard, Michel Cranga, Jean-Pierre Van Dorsselaere
Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 233-242, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89461
https://doi.org/10.1115/ICONE14-89461
View Paper titled, The Development of Severe Accident Codes at IRSN and Their Application to Support the Safety Assessment of EPR
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Topics: Accidents, Safety, Pressurized water reactors, Hydrogen, Combustion, Computational fluid dynamics, Containment, Flow (Dynamics), Heat transfer, Steam