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Proceedings Papers

Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor

Yali Qiu, Qin Zeng, Hongli Chen
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A031, August 8–12, 2022
Paper No: ICONE29-92104
DOI: https://doi.org/10.1115/ICONE29-92104
View Paper titled, Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor
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Topics: Fast neutron reactors, Radioisotopes, Coolants, Volatility, Accidents, Circuits, Computational fluid dynamics, Containment, Hazards, Irradiation (Radiation exposure)
Proceedings Papers

General Safety Assessment of Seismically Induced Hazards for NPPs

Guanghua Yang, Cuilian Yang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A054, August 8–12, 2022
Paper No: ICONE29-93121
DOI: https://doi.org/10.1115/ICONE29-93121
View Paper titled, General Safety Assessment of Seismically Induced Hazards for NPPs
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Topics: Earthquakes, Hazards, Nuclear power stations, Safety
Proceedings Papers

Applying the PIRT Approach to the Meteorological Hazards Wind and Rainfall in Relation to Industrial Needs: Benefits and Lessons Learned

Tiphaine Le Morvan, Arièle Défossez, Mickaël Kreitz
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A016, August 8–12, 2022
Paper No: ICONE29-90907
DOI: https://doi.org/10.1115/ICONE29-90907
View Paper titled, Applying the PIRT Approach to the Meteorological Hazards Wind and Rainfall in Relation to Industrial Needs: Benefits and Lessons Learned
Click here to open pdf in another window PDF for Applying the PIRT Approach to the Meteorological Hazards Wind and Rainfall in Relation to Industrial Needs: Benefits and Lessons Learned
Topics: Hazards, Meteorology, Nuclear power stations, Safety, Wind, Collaboration, Modeling, Natural phenomena, Nuclear engineers, Nuclear power
Proceedings Papers

PSA Application for UK HPR1000 ALARP Demonstration

Zhiwen Wang, Chunju Yang, Bing Zhang, Jinkai Wang, Huina Sang, Lingmei Xiao, Fei Wang, Ming Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A043, August 8–12, 2022
Paper No: ICONE29-93109
DOI: https://doi.org/10.1115/ICONE29-93109
View Paper titled, PSA Application for UK HPR1000 ALARP Demonstration
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Topics: China, Design, Fire, Floods, Hazards, Nuclear power, Probabilistic safety assessment, Risk, Safety, Spent nuclear fuels
Proceedings Papers

Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor

Risako Nakashima, Akari Koike, Takaaki Sakai, Norihiro Doda, Masaaki Tanaka
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A107, August 8–12, 2022
Paper No: ICONE29-93039
DOI: https://doi.org/10.1115/ICONE29-93039
View Paper titled, Quantitative Risk Assessment With CMMC Method on Abnormal Snowfall Incident for a Sodium-Cooled Fast Reactor
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Topics: Risk assessment, Sodium fast reactors, Hazards, Meteorology, Temperature, Dynamics (Mechanics), Probability, Chain, Climate change, Coolants
Proceedings Papers

Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building

Akemi Nishida, Byunghyun Choi, Tadahiko Shiomi, Manabu Kawata, Yinsheng Li
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A009, August 4–6, 2021
Paper No: ICONE28-64300
DOI: https://doi.org/10.1115/ICONE28-64300
View Paper titled, Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building
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Topics: Damage, Design, Earthquakes, Evaluation methods, Failure mechanisms, Hazards, Probabilistic risk assessment, Probability, Regulations, Safety
Proceedings Papers

Migration Characteristics of Sub-Source Items in Breach Occurrences

Xu Peng, Tian Ruifeng
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T08A008, August 4–6, 2021
Paper No: ICONE28-64606
DOI: https://doi.org/10.1115/ICONE28-64606
View Paper titled, Migration Characteristics of Sub-Source Items in Breach Occurrences
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Topics: Accidents, Aerosols, Computational fluid dynamics, Computer software, Coolants, Drag (Fluid dynamics), Flow (Dynamics), Fluids, Gravity (Force), Hazards
Proceedings Papers

Protection of Nuclear Power Plants Against Natural Hazards: Protection Principles Against Rare and Severe Natural Hazards for New Nuclear Power Plants

Vincent Coulon, Sébastien Christophe, Laurence Grammosenis, Luc Guinard, Hervé Cordier
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, V001T01A002, August 4–5, 2020
Paper No: ICONE2020-16185
DOI: https://doi.org/10.1115/ICONE2020-16185
View Paper titled, Protection of Nuclear Power Plants Against Natural Hazards: Protection Principles Against Rare and Severe Natural Hazards for New Nuclear Power Plants
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Topics: Hazards, Nuclear power stations, Pressurized water reactors, Safety
Proceedings Papers

Impact of Climate Change on EDF’s Nuclear Facilities: Climate Watch Approach

L. Guinard, S. Parey, H. Cordier, L. Grammosenis
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A021, August 4–5, 2020
Paper No: ICONE2020-16186
DOI: https://doi.org/10.1115/ICONE2020-16186
View Paper titled, Impact of Climate Change on EDF’s Nuclear Facilities: Climate Watch Approach
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Topics: Climate, Climate change, Hazards, Nuclear power stations, Safety
Proceedings Papers

Protection of Nuclear Power Plants Against Severe Winds: Impact of the Local Building Configuration on the Wind Speed to Consider

Arièle Défossez, Eric Dupont, Laurence Grammosenis, Hervé Cordier, Tiphaine Le Morvan
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A012, August 4–5, 2020
Paper No: ICONE2020-16136
DOI: https://doi.org/10.1115/ICONE2020-16136
View Paper titled, Protection of Nuclear Power Plants Against Severe Winds: Impact of the Local Building Configuration on the Wind Speed to Consider
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Topics: Computational fluid dynamics, Flow (Dynamics), Nuclear power stations, Pressurized water reactors, Safety, Wind velocity, Structures, Wind, Power stations, Storms
Proceedings Papers

Protection of Nuclear Power Plants Against Natural Hazards: Consideration for EDF’s Nuclear Facilities of Decamillennial Events (WENRA RL T4.2)

L. Guinard, S. Parey, L. Grammosenis, H. Cordier
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A022, August 4–5, 2020
Paper No: ICONE2020-16187
DOI: https://doi.org/10.1115/ICONE2020-16187
View Paper titled, Protection of Nuclear Power Plants Against Natural Hazards: Consideration for EDF’s Nuclear Facilities of Decamillennial Events (WENRA RL T4.2)
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Topics: Hazards, Nuclear power stations, Safety
Proceedings Papers

Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines

Antony M. Hurst, Pavitra Bansal
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, V001T06A016, August 4–5, 2020
Paper No: ICONE2020-16474
DOI: https://doi.org/10.1115/ICONE2020-16474
View Paper titled, Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines
Click here to open pdf in another window PDF for Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines
Topics: Finite element methods, Pipes, Underpinning, Hinges, Design, Finite element analysis, Light water reactors, Nuclear power stations, Nuclear reactor coolants, Stress
Proceedings Papers

Numerical Study of Tritium Mitigation Strategies for Fluoride Salt-Cooled High-Temperature Reactors

Sheng Zhang, Xiao Wu, Xiaodong Sun
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A025, August 4–5, 2020
Paper No: ICONE2020-16379
DOI: https://doi.org/10.1115/ICONE2020-16379
View Paper titled, Numerical Study of Tritium Mitigation Strategies for Fluoride Salt-Cooled High-Temperature Reactors
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Topics: Heat exchangers, High temperature, Design, Leakage, Light water reactors, Helium, Temperature, Algorithms, Coating processes, Coatings
Proceedings Papers

Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions

Jue Wang, Longze Li, Chen Hu, Wang Cong
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A002, July 22–26, 2018
Paper No: ICONE26-81159
DOI: https://doi.org/10.1115/ICONE26-81159
View Paper titled, Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions
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Topics: Nuclear power stations, Ocean engineering, Seawater, Boilers, Design, Dimensions, Hazards, Heat, Accidents, Computers
Proceedings Papers

iB1350: Part 2 — Level1 PRA Considering Optimization of Safety Systems for the iB1350

Tanaka Go, Sato Takashi, Komori Yuji, Matsumoto Keiji
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A025, July 22–26, 2018
Paper No: ICONE26-82552
DOI: https://doi.org/10.1115/ICONE26-82552
View Paper titled, iB1350: Part 2 — Level1 PRA Considering Optimization of Safety Systems for the iB1350
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Topics: Optimization, Safety, Accidents, Containment, Fukushima nuclear disaster, Japan, 2011, Heat, Boiling water reactors, Condensers (steam plant), Cooling systems, Cylinders
Proceedings Papers

European Utility Requirements for Advanced LWR Issue of EUR Revision E and Ongoing Assessments

Peter Chappell, Guillaume Jacquart, Giovanni Ferraro, Olli Kymäläinen
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A022, July 22–26, 2018
Paper No: ICONE26-82343
DOI: https://doi.org/10.1115/ICONE26-82343
View Paper titled, European Utility Requirements for Advanced LWR Issue of EUR Revision E and Ongoing Assessments
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Topics: Light water reactors, Nuclear power stations, Design, Safety, Performance, Public utilities, Construction, Engineering standards, Feedback, Fukushima nuclear disaster, Japan, 2011
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
Paper No: ICONE26-81893
DOI: 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

Experimental and Modeling Research on Leading Betavoltaic Technology

Thomas E. Adams, Shripad T. Revankar, Darrell S. Cheu, Peter Cabauy, Jesse Grant, Bret Elkind
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A056, July 22–26, 2018
Paper No: ICONE26-82475
DOI: https://doi.org/10.1115/ICONE26-82475
View Paper titled, Experimental and Modeling Research on Leading Betavoltaic Technology
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Topics: Modeling, Electrolytes, Leakage, Temperature, Corrosion, Defense industry, Electronics, Explosions, Fire, Hazards
Proceedings Papers

External Hazard Coinciding With Small Break LOCA Thermohydraulic Calculation With System Code ATHLET

Kai Kosowski, Marcus Seidl
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A005, July 22–26, 2018
Paper No: ICONE26-81815
DOI: https://doi.org/10.1115/ICONE26-81815
View Paper titled, External Hazard Coinciding With Small Break LOCA Thermohydraulic Calculation With System Code ATHLET
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Topics: Hazards, Emergencies, Cooling, Design, Nuclear power stations, Accidents, Boundary-value problems, Diesel engines, Pipes, Pumps
Proceedings Papers

Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors

Longze Li, Jue Wang, Yapei Zhang, G. H. Su
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A047, July 22–26, 2018
Paper No: ICONE26-82267
DOI: https://doi.org/10.1115/ICONE26-82267
View Paper titled, Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors
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Topics: Accidents, Sensitivity analysis, Small modular reactors, Containment, Fracture (Materials), Pressure, Heat sinks, Accident management, Boilers, Containment vessels