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Proceedings Papers

Transient Analysis of the Loss of Heat Sink Accident in a New Type of Megawatt Heat Pipe Reactor

Wang ZhenLan, Gou JunLi, Yuan LeQi, Shan JianQiang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A006, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131056
https://doi.org/10.1115/ICONE31-131056
View Paper titled, Transient Analysis of the Loss of Heat Sink Accident in a New Type of Megawatt Heat Pipe Reactor
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Topics: Accidents, Heat, Heat pipes, Heat sinks, Transient analysis, Transients (Dynamics)
Proceedings Papers

Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions

Emre Tatli, Sung Jin Lee, Jun Liao, Paolo Ferroni
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A020, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91821
https://doi.org/10.1115/ICONE29-91821
View Paper titled, Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions
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Topics: Cooling, Fast neutron reactors, Computational fluid dynamics, Design, Heat, Reactor vessels, Vessels, Water, Accidents, Accounting
Proceedings Papers

Application of 1D-CFD Coupling Method to Unprotected Loss of Heat Sink Event in EBR-II Focusing on Thermal Stratification in Cold Pool

Kazuo Yoshimura, Norihiro Doda, Tatsuya Fujisaki, Kennichi Igawa, Masaaki Tanaka, Hidemasa Yamano
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89259
https://doi.org/10.1115/ICONE29-89259
View Paper titled, Application of 1D-CFD Coupling Method to Unprotected Loss of Heat Sink Event in EBR-II Focusing on Thermal Stratification in Cold Pool
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Topics: Computational fluid dynamics, Heat sinks, Sodium fast reactors, Thermal stratification
Proceedings Papers

Development and Verification of Containment Heat Sink Module in Severe Accident Code

Zhi Yang, Peng Zhou, Lin Chen, Yixuan Cheng, Hao Zhang, Yanhua Yang, Yichen Mao
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A002, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91386
https://doi.org/10.1115/ICONE29-91386
View Paper titled, Development and Verification of Containment Heat Sink Module in Severe Accident Code
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Topics: Accidents, Containment, Heat sinks, Heat transfer
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93039
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

Study on the Fallback Time Analysis Method for Loss of Ultimate Heat Sink Under Normal Power Operation of Nuclear Power Unit

Zhao Zhang, Jun-Jie Yan, Gen Li, Dao-Tong Chong, Ming Liu, Zi-Chun Wang, Rong-Fa Shen
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A016, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92687
https://doi.org/10.1115/ICONE29-92687
View Paper titled, Study on the Fallback Time Analysis Method for Loss of Ultimate Heat Sink Under Normal Power Operation of Nuclear Power Unit
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Topics: Cooling, Heat sinks, Nuclear power, Water storage
Proceedings Papers

Investigation on the Flow and Heat Transfer Performance of Micro/Mini-Channel Liquid Cooling Heat Sink for Nuclear Control Chips

Xiao-Hu Yang, Zhaoli Zheng, Ping Song, Lie Chen, Chonghai Huang, Kai Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A003, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88841
https://doi.org/10.1115/ICONE29-88841
View Paper titled, Investigation on the Flow and Heat Transfer Performance of Micro/Mini-Channel Liquid Cooling Heat Sink for Nuclear Control Chips
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Topics: Computer simulation, Cooling, Flow (Dynamics), Heat sinks, Heat transfer
Proceedings Papers

Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D

Mian Xing, Linsen Li, Gang Zheng, Junlang Wen, Chunyuan Liu, Yeoh Eing Yee, Zhen Luo, Peidong Sun, Jinjun Feng
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, V001T04A002, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63220
https://doi.org/10.1115/ICONE28-63220
View Paper titled, Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D
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Topics: Fast neutron reactors, Safety, Transient analysis, Transients (Dynamics), Design, Reactor vessels, Accidents, Boilers, Conceptual design, Coolants
Proceedings Papers

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Fengyang Quan, Wei Li, Zikun Zhao, Xiao Zeng, Yong Guo, Yidan Yuan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A024, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64739
https://doi.org/10.1115/ICONE28-64739
View Paper titled, Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments
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Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux
Proceedings Papers

Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Kazuo Yoshimura, Norihiro Doda, Masaaki Tanaka, Hidemasa Yamano, Kennichi Igawa
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, V003T09A001, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62354
https://doi.org/10.1115/ICONE28-62354
View Paper titled, Validation of Evaluation Method of Feedback Reactivity for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
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Topics: Dynamics (Mechanics), Evaluation methods, Feedback, Heat sinks, Sodium fast reactors
Proceedings Papers

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

Sunil Nijhawan, YongMann Song
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, V001T01A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16633
https://doi.org/10.1115/ICONE2020-16633
View Paper titled, Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents
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Topics: Accidents, Heavy water reactors, Simulation, Fuels, Design, Modeling, Vessels, Damage, Failure, Fluids
Proceedings Papers

AP1000 ® Passive Cooling Containment Analysis of a Double-Ended LBLOCA With a 3D Gothic Model

Samanta Estevez-Albuja, Gonzalo Jimenez, Kevin Fernández-Cosials, César Queral, Zuriñe Goñi
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81886
https://doi.org/10.1115/ICONE26-81886
View Paper titled, AP1000 ® Passive Cooling Containment Analysis of a Double-Ended LBLOCA With a 3D Gothic Model
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Topics: Containment, Cooling, Safety, Heat, Pressure, Temperature, Accidents, Alternating current (Electricity), Containment buildings, Containment vessels
Proceedings Papers

Thermal Hydraulic Analysis of the CIRCE-HERO Pool-Type Facility

Bruno Gonfiotti, Gianluca Barone, Morena Angelucci, Daniele Martelli, Nicola Forgione, Alessandro Del Nevo, Mariano Tarantino
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A068, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82589
https://doi.org/10.1115/ICONE26-82589
View Paper titled, Thermal Hydraulic Analysis of the CIRCE-HERO Pool-Type Facility
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Topics: Boilers, Coolants, Engineering simulation, Fast neutron reactors, Flow (Dynamics), Fluids, Heat, Heat sinks, Leakage, Liquid metals
Proceedings Papers

Detailed Experimental and Analytical Study on Long Two-Phase Closed Thermosiphons Related to Passive Spent-Fuel Pool Cooling

Claudia Graß, Anne Krüssenberg, Rudi Kulenovic, Fabian Weyermann, Jörg Starflinger, Andreas Schaffrath
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A067, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81726
https://doi.org/10.1115/ICONE26-81726
View Paper titled, Detailed Experimental and Analytical Study on Long Two-Phase Closed Thermosiphons Related to Passive Spent-Fuel Pool Cooling
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Topics: Cooling, Spent nuclear fuels, Heat, Accidents, Design, Fluids, Geometry, Heat pipes, Heat sinks, Heat transfer
Proceedings Papers

SIRIO: An Experimental Facility for a New Heat Removal System Passively Controlled by Non-Condensable Gases

R. Marinari, M. Tarantino, F. S. Nitti, A. Alemberti, M. Caramello, A. Achilli, R. Ferri, E. Rizzo, F. Giannetti
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A054, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82379
https://doi.org/10.1115/ICONE26-82379
View Paper titled, SIRIO: An Experimental Facility for a New Heat Removal System Passively Controlled by Non-Condensable Gases
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Topics: Gases, Heat, Coolants, Safety, Design, Computer simulation, Freezing, Liquid metals, Solidification, Accidents
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82267
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
Proceedings Papers

Feasibility Assessment of Air-Cooling System As an Ultimate Heat Sink of the ATOM System

Doyoung Shin, Gwang Hyeok Seo, Min Wook Na, Sung Joong Kim, Yonghee Kim, Jeongik Lee
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A009, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81845
https://doi.org/10.1115/ICONE26-81845
View Paper titled, Feasibility Assessment of Air-Cooling System As an Ultimate Heat Sink of the ATOM System
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Topics: Atoms, Cooling, Heat sinks, Coolants, Steam, Condensation, Flow (Dynamics), Water, Air flow, Boron
Proceedings Papers

Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor

Ping Song, Dalin Zhang, Tangtao Feng, Shibao Wang, Yapei Zhang, Mingjun Wang, Suizheng Qiu, G. H. Su
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A061, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81630
https://doi.org/10.1115/ICONE26-81630
View Paper titled, Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor
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Topics: Heat, Sodium fast reactors, Accidents, Design, China, Circuits, Errors, Fast neutron reactors, Flow (Dynamics), Generation IV reactors
Proceedings Papers

Study on Effects of Environment Conditions on Essential Service Water System of Nuclear Power Station

Yang Ting, Li Guang Sheng, Li Zeng Fen, Peng Yue, Hu Jian
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A019, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66189
https://doi.org/10.1115/ICONE25-66189
View Paper titled, Study on Effects of Environment Conditions on Essential Service Water System of Nuclear Power Station
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Topics: Nuclear power stations, Water, Cooling, Economics , Safety, Construction, Design, Failure, Heat sinks, Reservoirs
Proceedings Papers

Radioisotope Thermophotovoltaic Generator Design and Performance Estimates for Terrestrial Applications

Xiawa Wang, Walker Chan, Veronika Stelmakh, Peter Fisher
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T13A008, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66607
https://doi.org/10.1115/ICONE25-66607
View Paper titled, Radioisotope Thermophotovoltaic Generator Design and Performance Estimates for Terrestrial Applications
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Topics: Design, Generators, Radioisotopes, Energy conversion, Heat, Heat sinks, Insulation, Circuits, Crystals, Design methodology