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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

Paper No: ICONE29-91821

DOI: https://doi.org/10.1115/ICONE29-91821

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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

Paper No: ICONE29-89259

DOI: https://doi.org/10.1115/ICONE29-89259

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Topics: Computational fluid dynamics, Heat sinks, Sodium fast reactors, Thermal stratification

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

Paper No: ICONE29-92687

DOI: https://doi.org/10.1115/ICONE29-92687

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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

Paper No: ICONE29-88841

DOI: https://doi.org/10.1115/ICONE29-88841

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Topics: Computer simulation, Cooling, Flow (Dynamics), Heat sinks, Heat transfer

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

Paper No: ICONE29-91386

DOI: https://doi.org/10.1115/ICONE29-91386

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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

Paper No: ICONE29-93039

DOI: https://doi.org/10.1115/ICONE29-93039

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Topics: Risk assessment, Sodium fast reactors, Hazards, Meteorology, Temperature, Dynamics (Mechanics), Probability, Chain, Climate change, Coolants

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

Paper No: ICONE28-63220

DOI: https://doi.org/10.1115/ICONE28-63220

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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

Paper No: ICONE28-64739

DOI: https://doi.org/10.1115/ICONE28-64739

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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

Paper No: ICONE28-62354

DOI: https://doi.org/10.1115/ICONE28-62354

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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

Paper No: ICONE2020-16633

DOI: https://doi.org/10.1115/ICONE2020-16633

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Topics: Accidents, Heavy water reactors, Simulation, Fuels, Design, Modeling, Vessels, Damage, Failure, Fluids

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

Paper No: ICONE26-81845

DOI: https://doi.org/10.1115/ICONE26-81845

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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

Paper No: ICONE26-81630

DOI: https://doi.org/10.1115/ICONE26-81630

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Topics: Heat, Sodium fast reactors, Accidents, Design, China, Circuits, Errors, Fast neutron reactors, Flow (Dynamics), Generation IV reactors

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

Paper No: ICONE26-81886

DOI: https://doi.org/10.1115/ICONE26-81886

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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

Paper No: ICONE26-82589

DOI: https://doi.org/10.1115/ICONE26-82589

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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

Paper No: ICONE26-81726

DOI: https://doi.org/10.1115/ICONE26-81726

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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

Paper No: ICONE26-82379

DOI: https://doi.org/10.1115/ICONE26-82379

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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

Paper No: ICONE26-82267

DOI: https://doi.org/10.1115/ICONE26-82267

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Topics: Accidents, Sensitivity analysis, Small modular reactors, Containment, Fracture (Materials), Pressure, Heat sinks, Accident management, Boilers, Containment vessels

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

Paper No: ICONE25-66189

DOI: https://doi.org/10.1115/ICONE25-66189

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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

Paper No: ICONE25-66607

DOI: https://doi.org/10.1115/ICONE25-66607

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Topics: Design, Generators, Radioisotopes, Energy conversion, Heat, Heat sinks, Insulation, Circuits, Crystals, Design methodology

Proceedings Papers

Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO2 As Working Fluid

Marcel Strätz, Jörg Starflinger, Rainer Mertz, Michael Seewald, Sebastian Schuster, Dieter Brillert

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T13A001, July 2–6, 2017

Paper No: ICONE25-66084

DOI: https://doi.org/10.1115/ICONE25-66084

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Topics: Cycles, Fluids, Heat, Supercritical carbon dioxide, Accidents, Brayton cycle, Design, Electricity (Physics), Heat sinks, Glass

2 3 4 5

NARROW

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

Radioisotope Thermophotovoltaic Generator Design and Performance Estimates for Terrestrial Applications

Cycle Calculations of a Small-Scale Heat Removal System With Supercritical CO2 As Working Fluid

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