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Proceedings Papers

An Assessment Method of Digital Human-Machine Interaction Complexity in Nuclear Power Plants: EHMIC

Xueyang Liu, Lu Cao
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A034, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93218
https://doi.org/10.1115/ICONE29-93218
View Paper titled, An Assessment Method of Digital Human-Machine Interaction Complexity in Nuclear Power Plants: EHMIC
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Topics: Boilers, Entropy, Machinery, Nuclear power stations, Rupture
Proceedings Papers

Evaluation of Detectability of Pump/Diagrid Link Rupture in Pool-Type Sodium-Cooled Fast Reactor

Yuichi Onoda, Masato Uchita, Minako Tokizaki, Hitoshi Okazaki
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A016, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91688
https://doi.org/10.1115/ICONE29-91688
View Paper titled, Evaluation of Detectability of Pump/Diagrid Link Rupture in Pool-Type Sodium-Cooled Fast Reactor
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Topics: Pumps, Rupture, Safety, Signals, Sodium fast reactors
Proceedings Papers

Consideration of Human Factors in SGTR Mitigation Strategy

Miaomiao Xu, Runcheng Li, Yunyin Chen, Wenying Ji, Zhikang Lin
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A023, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90151
https://doi.org/10.1115/ICONE29-90151
View Paper titled, Consideration of Human Factors in SGTR Mitigation Strategy
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Topics: Human factors, Pressurized water reactors, Safety, Design, Accidents, Boilers, Circuits, Containment, Rupture, Stress
Proceedings Papers

Numerical Study of Pressure Wave Effect in Steam Generator Tube Rupture Accident of Lead-Cooled Fast Reactor

Chong Qin, Kefan Zhang, Wenpei Feng, Hongli Chen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A065, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92114
https://doi.org/10.1115/ICONE29-92114
View Paper titled, Numerical Study of Pressure Wave Effect in Steam Generator Tube Rupture Accident of Lead-Cooled Fast Reactor
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Topics: Accidents, Boilers, Fast neutron reactors, Pressure, Rupture, Waves
Proceedings Papers

High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints

Shimei Bao
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A039, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92956
https://doi.org/10.1115/ICONE29-92956
View Paper titled, High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints
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Topics: Boilers, Gas cooled reactors, High temperature, High temperature materials, Rupture, Stress, Very high temperature reactors, Welded joints
Proceedings Papers

RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions

Masashi Sekine, Junichi Kaneko, Takeshi Takeda
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64117
https://doi.org/10.1115/ICONE28-64117
View Paper titled, RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions
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Topics: Accidents, Boilers, Pressurized water reactors, Rupture, Damage, Cooling, Earthquakes, Emergency core cooling systems, Failure, Feedwater
Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16897
https://doi.org/10.1115/ICONE2020-16897
View Paper titled, Probability of Rupture for WWER-1000 Main Piping
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Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations
Proceedings Papers

Study on Breakdown Features and Characteristics of Film at the Corrugated Plate Corner

Bo Wang, Bowen Chen, Bingzheng Ke, Ru Li, Gongqing Wang, Ruifeng Tian, Chuan Lu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A002, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16005
https://doi.org/10.1115/ICONE2020-16005
View Paper titled, Study on Breakdown Features and Characteristics of Film at the Corrugated Plate Corner
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Topics: Corners (Structural elements), Film thickness, Separation (Technology), Steam, Water, Air flow, Flow (Dynamics), Liquid films, Reynolds number, Boilers
Proceedings Papers

Experimental Study on Bubble Bursting and Droplet Releasing Characteristics Under Different Liquid Phase Conditions

Hao Chen, Haifeng Gu, Xiang Yu, Yanmin Zhou, Zhongning Sun, Jimin Wen
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A068, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82047
https://doi.org/10.1115/ICONE26-82047
View Paper titled, Experimental Study on Bubble Bursting and Droplet Releasing Characteristics Under Different Liquid Phase Conditions
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Topics: Bubbles, Drops, Aerosols, Drainage, Temperature, Emissions, Liquid films, Phase transitions, Photography, Probability
Proceedings Papers

Probabilistic Analysis of Creep-Induced SGTR for NPP

Wenjing Li, Wentao Zhu, Xinli Yu, Wei Wei
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81032
https://doi.org/10.1115/ICONE26-81032
View Paper titled, Probabilistic Analysis of Creep-Induced SGTR for NPP
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Topics: Creep, Nuclear power stations, Accidents, Probability, Accident management, Boilers, Failure, Pipes, Pressure, Probabilistic safety assessment
Proceedings Papers

Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000

Wonjun Choi, Taeseok Kim, Joongoo Jeon, Nam Kyung Kim, Sung Joong Kim
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82074
https://doi.org/10.1115/ICONE26-82074
View Paper titled, Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000
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Topics: Accidents, Sensitivity analysis, Nuclear fission, Pressure, Boilers, Feedwater, Flow (Dynamics), Valves, Accident management, Nuclear reactor coolants
Proceedings Papers

Investigation on Fission Products Release Mitigated by In-Containment Relief Valve Under SGTR Accident

Taeseok Kim, Wonjun Choi, Joongoo Jeon, Nam Kyung Kim, Sung Joong Kim
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A012, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82161
https://doi.org/10.1115/ICONE26-82161
View Paper titled, Investigation on Fission Products Release Mitigated by In-Containment Relief Valve Under SGTR Accident
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Topics: Accidents, Containment, Nuclear fission, Relief valves, Safety, Nuclides, Boilers, Flow (Dynamics), Valves, Containment buildings
Proceedings Papers

Analyzing Droplet Size Distributions Inside a Self-Priming Venturi Scrubber for Filtered Containment Venting Systems

P. Papadopoulos, T. Lind, H.-M. Prasser
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A044, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82227
https://doi.org/10.1115/ICONE26-82227
View Paper titled, Analyzing Droplet Size Distributions Inside a Self-Priming Venturi Scrubber for Filtered Containment Venting Systems
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Topics: Containment, Drops, Venturi tubes, Nozzles, Flow (Dynamics), Accidents, Design, Nuclear power stations, Aerosols, Boilers
Proceedings Papers

An Experimental Study of Liquid Flooding in Vertical Large Scale Rectangular Channel With the Counter-Current Flow of Air and Water Film

Kashuai Du, Po Hu, Shuwei Zhai, Xiaojie Yang, Weibo Wang
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A060, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82478
https://doi.org/10.1115/ICONE26-82478
View Paper titled, An Experimental Study of Liquid Flooding in Vertical Large Scale Rectangular Channel With the Counter-Current Flow of Air and Water Film
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Topics: Floods, Flow (Dynamics), Water, Temperature, Steel, Drops, Evaporation, Film flow, Flat plates, Glass
Proceedings Papers

Experimental Study on the Steam Line Break (SLB) Accident With the Steam Generator Tube Rupture (SGTR)

Yusun Park, Byoung Uhn Bae, Jongrok Kim, Jae Bong Lee, Hae Min Park, Nam Hyun Choi, Kyoung Ho Kang, Kyung Doo Kim
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A041, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81458
https://doi.org/10.1115/ICONE26-81458
View Paper titled, Experimental Study on the Steam Line Break (SLB) Accident With the Steam Generator Tube Rupture (SGTR)
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Topics: Accidents, Boilers, Rupture, Steam, Failure, Simulation, Water, Accident management, Flow (Dynamics), Fluids
Proceedings Papers

Pressurized Thermal Shock (PTS) Transient Scenarios Screening Analysis With TRACE

Roman Mukin, Ivor Clifford, Hakim Ferroukhi, Markus Niffenegger
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A069, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81749
https://doi.org/10.1115/ICONE26-81749
View Paper titled, Pressurized Thermal Shock (PTS) Transient Scenarios Screening Analysis With TRACE
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Topics: Thermal shock, Transients (Dynamics), Nuclear power stations, Vessels, Cooling, Reactor vessels, Accidents, Emergency core cooling systems, Pressure, Pressurized water reactors
Proceedings Papers

Evaluation of Jet Impact Region and Fluid Force Generated From Ruptured Pipes: Part 4 — Numerical Evaluation of Affected Region by Flashing Jet Flow

Ryo Morita, Shun Watanabe, Shiro Takahashi, Noriyuki Takamura
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A027, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82063
https://doi.org/10.1115/ICONE26-82063
View Paper titled, Evaluation of Jet Impact Region and Fluid Force Generated From Ruptured Pipes: Part 4 — Numerical Evaluation of Affected Region by Flashing Jet Flow
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Topics: Flashing, Fluids, Jets, Pipes, Computational fluid dynamics, Safety, Steam, Damage, Design, Evaluation methods
Proceedings Papers

Experimental Study on the Safety Injection Pump (SIP) Failure Accompanied by the Steam Generator Tube Rupture (SGTR)

Yusun Park, Byoung Uhn Bae, Jongrok Kim, Jae Bong Lee, Hae Min Park, Nam Hyun Choi, Kyoung Ho Kang
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A042, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81460
https://doi.org/10.1115/ICONE26-81460
View Paper titled, Experimental Study on the Safety Injection Pump (SIP) Failure Accompanied by the Steam Generator Tube Rupture (SGTR)
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Topics: Boilers, Failure, Pumps, Rupture, Safety, Accidents, Simulation, Accident management, Flow (Dynamics), Fluids
Proceedings Papers

Hydraulic Characteristics Research on SG Under Tube Plugging Operations Using FLUENT

Xiaohan Zhao, Mingjun Wang, Wenxi Tian, G. H. Su, Suizheng Qiu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A042, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81641
https://doi.org/10.1115/ICONE26-81641
View Paper titled, Hydraulic Characteristics Research on SG Under Tube Plugging Operations Using FLUENT
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Topics: Accidents, Boilers, Computer software, Coolants, Failure, Flow (Dynamics), Heat exchangers, Heat transfer, Maintenance, Nuclear fission
Proceedings Papers

CFD Modelling of Loss of Vacuum Accident (LOVA) for CFETR

Youyou Xu, Songlin Liu, Xiaoman Cheng, Xuebin Ma
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A032, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81970
https://doi.org/10.1115/ICONE26-81970
View Paper titled, CFD Modelling of Loss of Vacuum Accident (LOVA) for CFETR
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Topics: Accidents, Computational fluid dynamics, Modeling, Vacuum, Air flow, Dust, Leakage, Maintenance, Bridges (Structures), China