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Proceedings Papers

Study on Hydrogen Migration in Small Water Leak of Sodium-Cooled Fast Reactor

Xinjie Deng, Xuewu Cao
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A021, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81314
https://doi.org/10.1115/ICONE26-81314
View Paper titled, Study on Hydrogen Migration in Small Water Leak of Sodium-Cooled Fast Reactor
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Topics: Hydrogen, Sodium fast reactors, Water leakage, Sodium, Circuits, Water, Leakage, Boilers, Fracture (Materials), Heat
Proceedings Papers

Severe Accident Analysis With Spatial Discretized Model by MAAP: Part 1 — Parametric Study on Fukushima-Daiichi Unit-2

Kenichi Kanda, Yoshihisa Nishi, Kazuma Abe, Satoshi Nishimura, Koichi Nakamura, Masahiro Furuya, Atsushi Ui
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A031, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82129
https://doi.org/10.1115/ICONE26-82129
View Paper titled, Severe Accident Analysis With Spatial Discretized Model by MAAP: Part 1 — Parametric Study on Fukushima-Daiichi Unit-2
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Forensic sciences, Nuclear fission, Nuclear power stations, Pressure, Temperature, Transients (Dynamics), Underground injection
Proceedings Papers

Severe Accident Analysis With Spatial Discretized Model by MAAP: Part 2 — Parametric Study on Fukushima-Daiichi Unit-3

Yoshihisa Nishi, Kenichi Kanda, Kazuma Abe, Satoshi Nishimura, Koichi Nakamura, Masahiro Furuya, Atsushi Ui
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82018
https://doi.org/10.1115/ICONE26-82018
View Paper titled, Severe Accident Analysis With Spatial Discretized Model by MAAP: Part 2 — Parametric Study on Fukushima-Daiichi Unit-3
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Containment vessels, Nuclear fission, Nuclear power stations, Pressure, Sensitivity analysis, Simulation, Temperature, Transients (Dynamics)
Proceedings Papers

Assessment of Radiological Source Term Releases for Potential Severe Accident Scenarios in a PWR SFP

Kwang-Il Ahn, Jae-Uk Shin
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A004, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81633
https://doi.org/10.1115/ICONE26-81633
View Paper titled, Assessment of Radiological Source Term Releases for Potential Severe Accident Scenarios in a PWR SFP
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Topics: Accidents, Pressurized water reactors, Cooling, Emergencies, Fukushima nuclear disaster, Japan, 2011, Nuclear fission, Spent nuclear fuels, Underground injection
Proceedings Papers

Commissioning of CIRCE Facility for SGTR Experimental Investigation for HLMRs and Pre-Test Analysis by SIMMER-IV Code

Alessio Pesetti, Mariano Tarantino, Piero Gaggini, Giuseppe Polazzi, Nicola Forgione
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A039, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67419
https://doi.org/10.1115/ICONE25-67419
View Paper titled, Commissioning of CIRCE Facility for SGTR Experimental Investigation for HLMRs and Pre-Test Analysis by SIMMER-IV Code
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Topics: Boilers, Control equipment, Control systems, Data acquisition, Disks, Eutectic alloys, Flow (Dynamics), Heat exchangers, Hot water heating, Hydraulic lifts
Proceedings Papers

Severe Accident Analysis Using MAAP With Detailed Nodalization in Advanced Boiling Water Reactor

Hiromasa Chitose, Naoya Kamei, Ryusuke Kimura
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A025, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-68005
https://doi.org/10.1115/ICONE25-68005
View Paper titled, Severe Accident Analysis Using MAAP With Detailed Nodalization in Advanced Boiling Water Reactor
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Topics: Accidents, Boiling water reactors, Temperature, Flanges, Gaskets, Underground injection
Proceedings Papers

Fukushima Unit 2 Accident Simulation With MELCOR 2.1

Rafael Bocanegra, Valentino Di Marcello, Victor Sanchez, Gonzalo Jiménez
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A078, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61079
https://doi.org/10.1115/ICONE24-61079
View Paper titled, Fukushima Unit 2 Accident Simulation With MELCOR 2.1
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Simulation, Cooling systems, Containment, Disks, Failure mechanisms, Flow (Dynamics), Modeling, Rupture
Proceedings Papers

Assessment of SIMMER-III Code Based on Steam Generator Tube Rupture Experiments in LIFUS5/Mod2 Facility

Alessio Pesetti, Alessandro Del Nevo, Nicola Forgione
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, V002T06A025, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60711
https://doi.org/10.1115/ICONE24-60711
View Paper titled, Assessment of SIMMER-III Code Based on Steam Generator Tube Rupture Experiments in LIFUS5/Mod2 Facility
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Topics: Boilers, Rupture, Water, Pressure, Underground injection, Vessels, Boundary-value problems, Computer simulation, Computers, Cooling
Proceedings Papers

Test Section Design for SGTR Experimental Investigation in CIRCE Facility for HLMRS Supported by SIMMER-III Code

Alessio Pesetti, Mariano Tarantino, Nicola Forgione
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, V002T06A027, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60716
https://doi.org/10.1115/ICONE24-60716
View Paper titled, Test Section Design for SGTR Experimental Investigation in CIRCE Facility for HLMRS Supported by SIMMER-III Code
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Topics: Design, Rupture, Disks, Vessels, Boilers, Heat exchangers, Pressure, Transients (Dynamics), Underground injection, Water
Proceedings Papers

Development of High Efficiency Containment Venting System by Using AgX

Tadashi Narabayashi, Yuuhei Sugano, Hiroki Imaeda, Go Chiba, Nobuaki Sato, Koji Endo, Toshiki Kobayashi
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A076, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60999
https://doi.org/10.1115/ICONE24-60999
View Paper titled, Development of High Efficiency Containment Venting System by Using AgX
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Topics: Containment, Accidents, Filters, Countermeasures, Vents, Fukushima nuclear disaster, Japan, 2011, Underground injection, Aircraft, Chernobyl Nuclear Accident, Chornobyl, Ukraine, 1986, Coating processes
Proceedings Papers

Accident Analysis of Fukushima Daiichi Nuclear Power Plant Unit 2 by the SAMPSON Severe Accident Code

Atsuo Takahashi, Marco Pellegrini, Hideo Mizouchi, Hiroaki Suzuki, Masanori Naitoh
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A011, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30670
https://doi.org/10.1115/ICONE22-30670
View Paper titled, Accident Analysis of Fukushima Daiichi Nuclear Power Plant Unit 2 by the SAMPSON Severe Accident Code
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Water, Turbines, Pressure, Pumps, Steam, Boundary-value problems, Cooling systems
Proceedings Papers

Cold Water Injection and Rod Ejection Analysis of Annular Fueled PWRs by a Hybrid Lumped Parameter Model

Juliana P. Duarte, José de Jesus Rivero, Antonio Carlos M. Alvim, José Roberto C. Piqueira, Paulo F. F. Frutuoso e Melo
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A024, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30833
https://doi.org/10.1115/ICONE22-30833
View Paper titled, Cold Water Injection and Rod Ejection Analysis of Annular Fueled PWRs by a Hybrid Lumped Parameter Model
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Topics: Lumped parameter models, Pressurized water reactors, Underground injection, Fuels, Accidents, Transients (Dynamics), Feedback, Temperature, Doppler effect, Heat transfer
Proceedings Papers

SCDAP Model Improvement With QUENCH-06 Analysis

Hiroshi Madokoro, Koji Okamoto, Yuki Ishiwatari
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A010, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30086
https://doi.org/10.1115/ICONE22-30086
View Paper titled, SCDAP Model Improvement With QUENCH-06 Analysis
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Topics: Accident management, Computers, Electrical resistance, Heat transfer, Light water reactors, Modeling, Oxidation, Temperature profiles, Thermal properties, Uncertainty
Proceedings Papers

Analysis of Accident Progression of Fukushima Daiichi NPP by the SAMPSON Code

Masanori Naitoh, Marco Pellegrini, Hiroaki Suzuki, Hideo Mizouchi, Hidetoshi Okada
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A021, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30607
https://doi.org/10.1115/ICONE22-30607
View Paper titled, Analysis of Accident Progression of Fukushima Daiichi NPP by the SAMPSON Code
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Fuels, Heat, Buckling, Condensers (steam plant), Engines, Failure, Fire
Proceedings Papers

MELCOR Study of VVER-1000 Behavior in Case of Overheated Reactor Core Quenching

Pavlin P. Groudev, Antoaneta E. Stefanova, Petya I. Vryashkova
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A040, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30941
https://doi.org/10.1115/ICONE22-30941
View Paper titled, MELCOR Study of VVER-1000 Behavior in Case of Overheated Reactor Core Quenching
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Topics: Quenching (Metalworking), Fuels, Accidents, Reactor vessels, Accident management, Cladding systems (Building), Melting, Modeling, Porosity, Temperature
Proceedings Papers

Spent Fuel Pool Accidents in a Nordic BWR

Niina E. Könönen
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A020, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15641
https://doi.org/10.1115/ICONE21-15641
View Paper titled, Spent Fuel Pool Accidents in a Nordic BWR
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Topics: Accidents, Boiling water reactors, Spent nuclear fuels, Fuels, Cooling, Floods, Temperature, Air flow, Cladding systems (Building), Coolants
Proceedings Papers

OECD/NEA ROSA Project Experiment on Steam Condensation in PWR Horizontal Legs During Large-Break LOCA

Takeshi Takeda, Iwao Ohtsu, Hideo Nakamura
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 343-353, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54427
https://doi.org/10.1115/ICONE20-POWER2012-54427
View Paper titled, OECD/NEA ROSA Project Experiment on Steam Condensation in PWR Horizontal Legs During Large-Break LOCA
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Topics: Condensation, Pressurized water reactors, Steam, Emergency core cooling systems, Water, Drops, Flow (Dynamics), Accidents, Coolants, Failure
Proceedings Papers

Visual Experiments on the Subcooled Water Droplet Behavior in High Temperature Molten Metal

Yuan Zhou, Meng Lin, Zhengming Zhang, Lei Lei
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 639-643, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54930
https://doi.org/10.1115/ICONE20-POWER2012-54930
View Paper titled, Visual Experiments on the Subcooled Water Droplet Behavior in High Temperature Molten Metal
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Topics: Coolants, Drops, Explosions, Fuels, High temperature, Metals, Steam, Subcooling, Underground injection, Water
Proceedings Papers

Severe Accident Analysis for BWR With Containment Outer Pool

Koki Yoshimura, Kohei Hisamochi
Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 809-817, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55131
https://doi.org/10.1115/ICONE20-POWER2012-55131
View Paper titled, Severe Accident Analysis for BWR With Containment Outer Pool
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Topics: Accidents, Boiling water reactors, Containment, Pressure, Temperature, Cooling, Cooling systems, Failure, Shells, Underground injection
Proceedings Papers

An Evaluation of a Direct Corium Cooling Method for the Ex-Vessel Melt Retention

Kwang Soon Ha, Hwan Yeol Kim, Jongtae Kim, Jong Hwa Park
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 359-367, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29141
https://doi.org/10.1115/ICONE18-29141
View Paper titled, An Evaluation of a Direct Corium Cooling Method for the Ex-Vessel Melt Retention
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Topics: Cooling, Vessels, Steam, Ablation (Vaporization technology), Accidents, Concretes, Coolants, Explosions, Water, Containment