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Proceedings Papers

Analysis and Mitigation Strategy on the Decreasing Opening of Thermal Pressurizer Pilot Operated Safety Relief Valves

Wensheng Hu, Chaofan Guo, Haisheng Zhao, Zhaoji Ruan, Jidong Min, Pencheng Du, Xinxin Wang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A031, August 8–12, 2022

Paper No: ICONE29-92099

DOI: https://doi.org/10.1115/ICONE29-92099

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Topics: Leakage, Relief valves, Safety

Proceedings Papers

The Solenoid Valve for Main Steam Relief Valve Adapted Under Severe Accident

Nobuo Kojima, Koji Nishino, Keisuke Sakemura, Kengo Kobayashi

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, V001T01A001, August 4–5, 2020

Paper No: ICONE2020-16030

DOI: https://doi.org/10.1115/ICONE2020-16030

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Topics: Accidents, Relief valves, Solenoids, Steam, Valves

Proceedings Papers

Transient Analysis of Dedicated Pressure Relief Valve Under High-Pressure Condition in Severe Accident for Tianwan 56 Nuclear Power Plant

Youyou Xu, Jian Deng, Xiaoji Wang, Lingjun Wu, Ming Zhang, Libo Qian, Rong Cai, Lei Zhong, Zhengyu Du

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A059, August 4–5, 2020

Paper No: ICONE2020-16847

DOI: https://doi.org/10.1115/ICONE2020-16847

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Topics: Accidents, Feedwater, High pressure (Physics), Nuclear power stations, Relief valves, Transient analysis

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

Paper No: ICONE26-82074

DOI: https://doi.org/10.1115/ICONE26-82074

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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

Paper No: ICONE26-82161

DOI: https://doi.org/10.1115/ICONE26-82161

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Topics: Accidents, Containment, Nuclear fission, Relief valves, Safety, Nuclides, Boilers, Flow (Dynamics), Valves, Containment buildings

Proceedings Papers

Applying Computational Fluid Dynamics Methodologies to Hydro-Dynamic Loads in the Suppression Pool of a BWR

David Mauritzson, Sven Perzon, Thomas Probert

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A035, July 22–26, 2018

Paper No: ICONE26-82167

DOI: https://doi.org/10.1115/ICONE26-82167

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Topics: Boiling water reactors, Computational fluid dynamics, Stress, Containment, Condensation, Resolution (Optics), Drag (Fluid dynamics), Modeling, Vibration, Design

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

Paper No: ICONE26-81749

DOI: https://doi.org/10.1115/ICONE26-81749

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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

Impact of Switching Time Interval for Dual Intakes on Workers in Main Control Room During Accidents

Xue Na, Lin Hongtao, Liu Xinjian, Mao Yawei, Qiu Lin

Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A037, July 2–6, 2017

Paper No: ICONE25-67742

DOI: https://doi.org/10.1115/ICONE25-67742

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Topics: Accidents, Control rooms, Contamination, Instrumentation, Meteorology, Ventilation, Containment, Leakage, Radioactive substances, Relief valves

Proceedings Papers

Three Pressure Peaks Analysis for the TEPCO Fukushima Daiichi Unit 2 by the SAMPSON Code

Chiaki Kino, Hiroaki Suzuki, Itsuo Yoshioka, Hidetoshi Okada, Masanori Naitoh

Paper No: ICONE25-68020

DOI: https://doi.org/10.1115/ICONE25-68020

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Topics: Fukushima nuclear disaster, Japan, 2011, Pressure, Accidents, Nuclear decommissioning, Relief valves, Safety, Simulation results

Proceedings Papers

The Demonstrated Function of PLR Pump Mechanical Seal Under SBO Conditions

Toshiyuki Yoshioka, Takashi Motani, Atsushi Fujimaru, Koji Yamada, Kunihiro Hasegawa, Takeshi Shimizu, Hiroyuki Torigoe

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A072, July 2–6, 2017

Paper No: ICONE25-66919

DOI: https://doi.org/10.1115/ICONE25-66919

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Topics: Pumps, Leakage, Boiling water reactors, Nuclear reactor coolants, Safety, Failure, Pressurized water reactors, Accidents, Fukushima nuclear disaster, Japan, 2011, Licensing

Proceedings Papers

The Early Depressurization Method for the Vapor Generation at the Top of Reactor Vessel

Hokuto Tsuruoka, Shinya Miyata, Manabu Maruyama, Daisuke Kanamori

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A033, June 26–30, 2016

Paper No: ICONE24-60520

DOI: https://doi.org/10.1115/ICONE24-60520

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Topics: Accidents, Boilers, Boiling, Computers, Condensation, Coolants, Leakage, Modeling, Nuclear reactor coolants, Nuclear reactor cooling

Proceedings Papers

Experimental Research on Characteristics of Passive Residual Heat Removal System for Small Modular Reactors Under the Station Blackout Accident

Xiaodong Lu, Chuanxin Peng, Yan Zhang, Xuesong Bai, Yuanfeng Zan, Wenbin Zhuo, Xiao Yan

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A036, June 26–30, 2016

Paper No: ICONE24-60527

DOI: https://doi.org/10.1115/ICONE24-60527

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Topics: Accidents, Heat, Small modular reactors, Water, Pressure, Boilers, China, Containment, Coolants, Cooling

Proceedings Papers

Numerical and Theoretical Study on Parameter Selection of Acoustic Load Test of Steam Dryer

Jia Zhong, Han Wang, Nan Wang, Jinyi Zhang, Yujia Liu, Wen Liu, Kai Zhang

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A079, June 26–30, 2016

Paper No: ICONE24-61023

DOI: https://doi.org/10.1115/ICONE24-61023

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Topics: Sound pressure, Steam, Acoustics, Pipes, Resonance, Flow (Dynamics), Cracking (Materials), Engineering prototypes, Failure, Fracture (Process)

Proceedings Papers

Study on the Break Accidents of the HTR-PM Primary Loop

Minggang Lang, Ximing Sun, Yanhua Zheng

Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A006, June 26–30, 2016

Paper No: ICONE24-60113

DOI: https://doi.org/10.1115/ICONE24-60113

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Topics: Accidents, Helium, Containment, Coolants, Pressure, Temperature, Boilers, Design, High temperature, Leakage

Proceedings Papers

Analysis and Evaluation of the Setting Value Drift of SEBIM Relief Valve Used in Nuclear Power Plant

Xiaochuan Yang, Chunlei Luo, Meng Qu, Rongfa Shen, Yinhui Che

Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A035, July 29–August 2, 2013

Paper No: ICONE21-16281

DOI: https://doi.org/10.1115/ICONE21-16281

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Topics: Nuclear power stations, Relief valves, Overpressure protection, Safety, Valves, Failure mechanisms, Nuclear industry, Pipelines, Power stations, Pressure

Proceedings Papers

TRACE/PARCS Analysis of Full Isolation Startup Test for Lungmen ABWR

Ai-Ling Ho, Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 313-320, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54174

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54174

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Topics: Delays, Domes (Structural elements), Nuclear power stations, Pressure, Pumps, Relief valves, Scram, Signals, Valves, Water

Proceedings Papers

Safety Assurance for Boiling Water Reactors (BWRs) Beyond Design Basis

Salomon Levy

Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 735-750, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54674

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54674

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Topics: Boiling water reactors, Design, Safety, Fukushima nuclear disaster, Japan, 2011, Water, Containment, Cooling, Failure, Heat sinks, Nuclear power stations

Proceedings Papers

Importance of Reactor Heat Transport System Overpressure Protection System Under Severe Accident Conditions With Special Reference to CANDU Reactors

Sunil Nijhawan

Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 653-662, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54301

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54301

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Topics: Accidents, Heat, Overpressure protection, Design, Relief valves, Valves, Safety, Containment, Failure, Pressure

Proceedings Papers

Dynamic Analysis of Including New Loads on Spent Fuel Storage Rack

YaoLong Tsai, TaiPing Tsai, ChaoJen Li, Li-Hua Wang, TeWei Fan, ChangPin Chou

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 549-552, May 17–21, 2010

Paper No: ICONE18-29721

DOI: https://doi.org/10.1115/ICONE18-29721

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Topics: Dynamic analysis, Spent fuel storage, Stress, Safety, Accidents, Coolants, Degrees of freedom, Fuels, Regulations, Relief valves

Proceedings Papers

Numerical Evaluation of Fluctuating Pressure at Stub Pipes in Actual BWR Main Steam Lines

Ryo Morita, Shiro Takahashi, Fumio Inada, Yukio Ogawa

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 463-468, May 17–21, 2010

Paper No: ICONE18-29355

DOI: https://doi.org/10.1115/ICONE18-29355

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Topics: Boiling water reactors, Pipes, Pressure, Steam, Resonance, Acoustics, Fluctuations (Physics), Nuclear power stations, Power uprate, Evaluation methods

NARROW

Analysis and Mitigation Strategy on the Decreasing Opening of Thermal Pressurizer Pilot Operated Safety Relief Valves

The Solenoid Valve for Main Steam Relief Valve Adapted Under Severe Accident

Transient Analysis of Dedicated Pressure Relief Valve Under High-Pressure Condition in Severe Accident for Tianwan 56 Nuclear Power Plant

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

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

Applying Computational Fluid Dynamics Methodologies to Hydro-Dynamic Loads in the Suppression Pool of a BWR

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

Impact of Switching Time Interval for Dual Intakes on Workers in Main Control Room During Accidents

Three Pressure Peaks Analysis for the TEPCO Fukushima Daiichi Unit 2 by the SAMPSON Code

The Demonstrated Function of PLR Pump Mechanical Seal Under SBO Conditions

The Early Depressurization Method for the Vapor Generation at the Top of Reactor Vessel

Experimental Research on Characteristics of Passive Residual Heat Removal System for Small Modular Reactors Under the Station Blackout Accident

Numerical and Theoretical Study on Parameter Selection of Acoustic Load Test of Steam Dryer

Study on the Break Accidents of the HTR-PM Primary Loop

Analysis and Evaluation of the Setting Value Drift of SEBIM Relief Valve Used in Nuclear Power Plant

TRACE/PARCS Analysis of Full Isolation Startup Test for Lungmen ABWR

Safety Assurance for Boiling Water Reactors (BWRs) Beyond Design Basis

Importance of Reactor Heat Transport System Overpressure Protection System Under Severe Accident Conditions With Special Reference to CANDU Reactors

Dynamic Analysis of Including New Loads on Spent Fuel Storage Rack

Numerical Evaluation of Fluctuating Pressure at Stub Pipes in Actual BWR Main Steam Lines

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