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Proceedings Papers

Design and Performance Verification of Passive Core Cooling System Strainer in Advanced Nuclear Power Plants of China

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Ruolin Huang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A051, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134892
https://doi.org/10.1115/ICONE31-134892
View Paper titled, Design and Performance Verification of Passive Core Cooling System Strainer in Advanced Nuclear Power Plants of China
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Topics: China, Cooling, Cooling systems, Design, Emergency core cooling systems, Nuclear power stations, Loss of coolant accidents, Filters, Aluminum, Coating processes
Proceedings Papers

The Effect of Liquid and Wall Properties Toward the Increase of Wetting Velocity in the Case of Using Multiple Plates in the Top-Reflood Vertical Surfaces

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Akbari, Hiroyuki Umebayashi, Tomio Okawa
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A020, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134362
https://doi.org/10.1115/ICONE31-134362
View Paper titled, The Effect of Liquid and Wall Properties Toward the Increase of Wetting Velocity in the Case of Using Multiple Plates in the Top-Reflood Vertical Surfaces
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Topics: Drops, Emergency core cooling systems, Loss of coolant accidents, Plates (structures), Wetting
Proceedings Papers

Study on Interfacing System LOCA of VVER-1200

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Jinyan Du, Fangyu Dong, Chao Ma
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89803
https://doi.org/10.1115/ICONE29-89803
View Paper titled, Study on Interfacing System LOCA of VVER-1200
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Topics: Accidents, Containment, Coolants, Damage, Defense industry, Emergency core cooling systems, High pressure (Physics), Nuclear power stations, Nuclear reactor coolants, Pressure
Proceedings Papers

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

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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

Investigation of VVER-440 Confinement Response During DBA After Leaktightness Improvement

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Hovhannes Hovhannisyan, Tsolak Malakyan, Armen Amirjanyan
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A004, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16038
https://doi.org/10.1115/ICONE2020-16038
View Paper titled, Investigation of VVER-440 Confinement Response During DBA After Leaktightness Improvement
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Topics: Accidents, Cavitation, Design, Emergency core cooling systems, Nuclear power stations, Pumps, Safety, Sprays
Proceedings Papers

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

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Zefeng Wang, Jian Deng, Libo Qian, Rong Cai, Jinbiao Xiong, Lei Zhong, Yugao Ma
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A038, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16709
https://doi.org/10.1115/ICONE2020-16709
View Paper titled, Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water
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Topics: Heat transfer, Pool boiling, Quenching (Metalworking), Transients (Dynamics), Water, Temperature, Film boiling, Zirconium, Thermocouples, Accidents
Proceedings Papers

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

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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

Identification of Gas Accumulation Susceptibility in NPP’s Safety Related Systems and Operability Evaluation due to Gas Transportation

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Zhen-Yu Hung, Pei-Hsun Huang, Chao-Jen Li
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A004, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81074
https://doi.org/10.1115/ICONE26-81074
View Paper titled, Identification of Gas Accumulation Susceptibility in NPP’s Safety Related Systems and Operability Evaluation due to Gas Transportation
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Topics: Safety, Transportation systems, Computer software, Containment, Corrective actions, Design, Emergency core cooling systems, Experimental analysis, Licensing, Nuclear power plant operations
Proceedings Papers

Numerical Simulations of Two-Phase Flow in a Fuel Assembly of Blockage due to LOCA

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Jingwen Ren, Fenglei Niu, Weiqian Zhuo, Da Wang
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A026, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66729
https://doi.org/10.1115/ICONE25-66729
View Paper titled, Numerical Simulations of Two-Phase Flow in a Fuel Assembly of Blockage due to LOCA
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Topics: Computer simulation, Fuels, Manufacturing, Two-phase flow, Pressure drop, Particulate matter, Water, Flow (Dynamics), Accidents, Bubbles
Proceedings Papers

Assessment on Direct Debris Interaction at High Pressure Melt Ejection Scenario in Level 2 PSA

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Naoki Hirokawa, Hiromasa Chitose, Kohei Hisamochi
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A038, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67635
https://doi.org/10.1115/ICONE25-67635
View Paper titled, Assessment on Direct Debris Interaction at High Pressure Melt Ejection Scenario in Level 2 PSA
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Topics: Accidents, Boiling water reactors, Containment, Damage, Emergency core cooling systems, Failure, Heating, High pressure (Physics), Particulate matter, Probabilistic safety assessment
Proceedings Papers

Sensitivity Study of LOCA-Generated Debris on the Pressure Drop of Fuel Assembly

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Hammad Aslam Bhatti, Zhangpeng Guo, Weiqian Zhuo, Shahroze Ahmed, Da Wang, Fenglei Niu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A081, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67122
https://doi.org/10.1115/ICONE25-67122
View Paper titled, Sensitivity Study of LOCA-Generated Debris on the Pressure Drop of Fuel Assembly
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Topics: Fuels, Manufacturing, Pressure drop, Emergency core cooling systems, Containment, Coolants, Cooling, Glass, Pressurized water reactors, Accidents
Proceedings Papers

Heat Transfer Characteristics of Downward Facing Hot Horizontal Surfaces Using Mist Jet Impingement

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Ashutosh Kumar Yadav, Parantak Sharma, Avadhesh Kumar Sharma, Mayank Modak, Vishal Nirgude, Santosh K. Sahu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A099, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67537
https://doi.org/10.1115/ICONE25-67537
View Paper titled, Heat Transfer Characteristics of Downward Facing Hot Horizontal Surfaces Using Mist Jet Impingement
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Topics: Heat transfer, Cooling, Water, Emergency core cooling systems, Heat flux, Impingement cooling, Nozzles, Sprays, Steel, Accidents
Proceedings Papers

Analysis and Validation of Wilks Nonparametric Uncertainty Method for Best-Estimate Calculations in Nuclear Safety

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Deng Cheng-Cheng, Liu Wei-Li, Yang Jun, Wu Qiao
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A015, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66655
https://doi.org/10.1115/ICONE25-66655
View Paper titled, Analysis and Validation of Wilks Nonparametric Uncertainty Method for Best-Estimate Calculations in Nuclear Safety
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Topics: Safety, Uncertainty, Emergency core cooling systems, Stability, Accidents, Flow (Dynamics), Nuclear power stations, Response surface methodology, Uncertainty analysis, Uncertainty quantification
Proceedings Papers

Long-Term Cooling Strategy for the Primary Containment Vessel of the Kashiwazaki-Kariwa Nuclear Power Station in a Severe Accident

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Satoshi Kawaguchi, Satoshi Mizuno, Yoshihiro Oyama
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A019, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67317
https://doi.org/10.1115/ICONE25-67317
View Paper titled, Long-Term Cooling Strategy for the Primary Containment Vessel of the Kashiwazaki-Kariwa Nuclear Power Station in a Severe Accident
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Topics: Accidents, Containment vessels, Cooling, Nuclear power stations, Heat, Temperature, Heat exchangers, Water, Pumps, Reliability
Proceedings Papers

iB1350: A Generation III.7 Reactor After the Fukushima Daiichi Accident

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Takashi Sato, Keiji Matsumoto, Kenji Hosomi, Keisuke Taguchi
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, V002T06A022, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60523
https://doi.org/10.1115/ICONE24-60523
View Paper titled, iB1350: A Generation III.7 Reactor After the Fukushima Daiichi Accident
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Safety, Containment, Design, Emergency core cooling systems, Failure, Aircraft, Boiling water reactors, Construction
Proceedings Papers

Simulation of Direct Contact Condensation Using Large Scale Interface Multifluid Model

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Vinesh H. Gada, Mohit P. Tandon, Jebin Elias, Andrew Splawski, Simon Lo
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A023, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60786
https://doi.org/10.1115/ICONE24-60786
View Paper titled, Simulation of Direct Contact Condensation Using Large Scale Interface Multifluid Model
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Topics: Condensation, Simulation, Steam, Water, Damping, Drag (Fluid dynamics), Emergency core cooling systems, Flow (Dynamics), Heat, Nuclear power
Proceedings Papers

Investigations About Released Debris and Corrosion Products and Their Impact to Head Loss Build Up and Decay Heat Removal Under Water-Chemical PWR-LOCA Conditions

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Stefan Renger, Sören Alt, Wolfgang Kästner, André Seeliger
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A012, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60261
https://doi.org/10.1115/ICONE24-60261
View Paper titled, Investigations About Released Debris and Corrosion Products and Their Impact to Head Loss Build Up and Decay Heat Removal Under Water-Chemical PWR-LOCA Conditions
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Topics: Corrosion, Heat, Pressurized water reactors, Water, Coolants, Emergency core cooling systems, Filters, Flow (Dynamics), Heat transfer, Safety
Proceedings Papers

Experimental Investigation of Rewetting During Quenching of Hot Surface by Round Jet Impingement Using Al 2 O 3 –Water Nanofluids

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Avadhesh K. Sharma, Mayank Modak, Santosh K. Sahu
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A056, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60732
https://doi.org/10.1115/ICONE24-60732
View Paper titled, Experimental Investigation of Rewetting During Quenching of Hot Surface by Round Jet Impingement Using Al 2 O 3 –Water Nanofluids
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Topics: Nanofluids, Quenching (Metalworking), Water, Cooling, Emergency core cooling systems, Fuel rods, Heat, Temperature, Accidents, Coolants
Proceedings Papers

The Effects of Subcooling on Quenching of a Vertical Brass Cylinder With Heating Power

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Yuan-Hong Ho, Ming-Xi Ho, Chin Pan
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T04A001, June 28–July 2, 2015
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2015-49307
https://doi.org/10.1115/NUCLRF2015-49307
View Paper titled, The Effects of Subcooling on Quenching of a Vertical Brass Cylinder With Heating Power
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Topics: Brass (Metal), Cylinders, Heating, Quenching (Metalworking), Subcooling, Film boiling, Coolants, Heat, Nuclear power stations, Water
Proceedings Papers

Head Loss Through Fibrous Beds Generated on Different Types of Containment Sump Strainers

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Saya Lee, Suhaeb Abdulsattar, Yassin A. Hassan
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A069, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31233
https://doi.org/10.1115/ICONE22-31233
View Paper titled, Head Loss Through Fibrous Beds Generated on Different Types of Containment Sump Strainers
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Topics: Containment, Emergency core cooling systems, Light water reactors, Safety, Accidents, Coolants, Countermeasures, Insulation, Nuclear power stations, Pressure drop