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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

Paper No: ICONE29-89268

DOI: https://doi.org/10.1115/ICONE29-89268

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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

Paper No: ICONE29-91957

DOI: https://doi.org/10.1115/ICONE29-91957

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Topics: Circuits, Fukushima nuclear disaster, Japan, 2011, Safety, Underground injection

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

Paper No: ICONE28-65217

DOI: https://doi.org/10.1115/ICONE28-65217

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Topics: Ablation (Vaporization technology), Concretes, Temperature, 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

Paper No: ICONE28-64737

DOI: https://doi.org/10.1115/ICONE28-64737

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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

Paper No: ICONE28-62115

DOI: https://doi.org/10.1115/ICONE28-62115

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Topics: Heat transfer, Underground injection, Zirconium

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

Paper No: ICONE2020-16737

DOI: https://doi.org/10.1115/ICONE2020-16737

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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

Paper No: ICONE2020-16388

DOI: https://doi.org/10.1115/ICONE2020-16388

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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

Paper No: ICONE26-81633

DOI: https://doi.org/10.1115/ICONE26-81633

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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

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

Paper No: ICONE26-81314

DOI: https://doi.org/10.1115/ICONE26-81314

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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

Paper No: ICONE26-82129

DOI: https://doi.org/10.1115/ICONE26-82129

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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

Paper No: ICONE26-82018

DOI: https://doi.org/10.1115/ICONE26-82018

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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

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

Paper No: ICONE25-68005

DOI: https://doi.org/10.1115/ICONE25-68005

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Topics: Accidents, Boiling water reactors, Temperature, Flanges, Gaskets, 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

Paper No: ICONE25-67419

DOI: https://doi.org/10.1115/ICONE25-67419

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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

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

Paper No: ICONE24-60711

DOI: https://doi.org/10.1115/ICONE24-60711

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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

Paper No: ICONE24-60716

DOI: https://doi.org/10.1115/ICONE24-60716

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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

Paper No: ICONE24-61079

DOI: https://doi.org/10.1115/ICONE24-61079

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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

Paper No: ICONE24-60999

DOI: https://doi.org/10.1115/ICONE24-60999

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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

Paper No: ICONE22-30607

DOI: https://doi.org/10.1115/ICONE22-30607

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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

Paper No: ICONE22-30941

DOI: https://doi.org/10.1115/ICONE22-30941

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Topics: Quenching (Metalworking), Fuels, Accidents, Reactor vessels, Accident management, Cladding systems (Building), Melting, Modeling, Porosity, Temperature

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

Paper No: ICONE22-30670

DOI: https://doi.org/10.1115/ICONE22-30670

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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Water, Turbines, Pressure, Pumps, Steam, Boundary-value problems, Cooling systems

NARROW

Nuclear Power Plant Design Optimization Based on Risk-Informed Method

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

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

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

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

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

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

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

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

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

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

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

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

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

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

Fukushima Unit 2 Accident Simulation With MELCOR 2.1

Development of High Efficiency Containment Venting System by Using AgX

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

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

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

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