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Proceedings Papers

Nuclear Power Plant Design Optimization Based on Risk-Informed Method

Wenjing Li, Yu Liu, Gaopeng Wang, Xinli Yu
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89268
https://doi.org/10.1115/ICONE29-89268
View Paper titled, Nuclear Power Plant Design Optimization Based on Risk-Informed Method
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Topics: Nuclear design, Optimization, Risk, Design, Nuclear power stations, Accidents, Cavities, Vessels, China, Damage
Proceedings Papers

Access Time and Safety Benefit Analysis of Additional Temporary Water Injection Measures on Primary After the Fukushima

Weidong Liu, Zhao Wang, LeiLei Liu, Kuan Zhang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A030, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91957
https://doi.org/10.1115/ICONE29-91957
View Paper titled, Access Time and Safety Benefit Analysis of Additional Temporary Water Injection Measures on Primary After the Fukushima
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Topics: Circuits, Fukushima nuclear disaster, Japan, 2011, Safety, Underground injection
Proceedings Papers

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Yubin Zhang
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, V003T08A011, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64737
https://doi.org/10.1115/ICONE28-64737
View Paper titled, Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel
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Topics: Numerical analysis, Reactor vessels, Thermal shock, Accidents, Computational fluid dynamics, Computer software, Coolants, Flow (Dynamics), Mechanical structures, Nozzles
Proceedings Papers

Experimental Study on Heat Transfer Characteristics of Water Injection on Molten Pool With Low Mass Fraction of Zirconium

Zongyang Li, Huajian Chang, Fangfang Fang, Kun Han, Botao Hao, Lian Chen
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A005, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62115
https://doi.org/10.1115/ICONE28-62115
View Paper titled, Experimental Study on Heat Transfer Characteristics of Water Injection on Molten Pool With Low Mass Fraction of Zirconium
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Topics: Heat transfer, Underground injection, Zirconium
Proceedings Papers

A New Insight Into Molten Corium Concrete Interaction With Concrete Ablation Analysis for Mitigation Scheme

Ilyas Khurshid, Amidu Muritala Alade, Yacine Addad, Imran Afgan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A028, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65217
https://doi.org/10.1115/ICONE28-65217
View Paper titled, A New Insight Into Molten Corium Concrete Interaction With Concrete Ablation Analysis for Mitigation Scheme
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Topics: Ablation (Vaporization technology), Concretes, Temperature, Underground injection
Proceedings Papers

Development of a Water Injection System Fusible Plug for Severe Accidents at Nuclear Power Plants

Sei Hirano, Daisuke Hirasawa, Yoshihisa Kiyotoki, Keisuke Sakemura, Keiji Sasaki, Yuta Fukuda
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A051, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16737
https://doi.org/10.1115/ICONE2020-16737
View Paper titled, Development of a Water Injection System Fusible Plug for Severe Accidents at Nuclear Power Plants
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Topics: Accidents, Alloys, Fusibles (Textiles), Nuclear power stations, Underground injection, Vessels
Proceedings Papers

Numerical Simulation of Concrete Ablation and Corium Cooling for Molten Corium-Concrete Interaction (MCCI)

Zhichun Xu, Yapei Zhang, G. H. Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A026, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16388
https://doi.org/10.1115/ICONE2020-16388
View Paper titled, Numerical Simulation of Concrete Ablation and Corium Cooling for Molten Corium-Concrete Interaction (MCCI)
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Topics: Ablation (Vaporization technology), Computer simulation, Concretes, Cooling, Light water reactors, Reactor vessels, Accidents, Cavities, Containment, Flow (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

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

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

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

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

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

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

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

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

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