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Proceedings Papers

Evaluation of Effect of Depressurization Timing on the Thermal Load To Primary Containment Vessel During Severe Accident at BWR

Taisei Matsumoto, Akifumi Yamaji, Daisuke Fujiwara
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A005, August 8–12, 2022
Paper No: ICONE29-90648
https://doi.org/10.1115/ICONE29-90648
View Paper titled, Evaluation of Effect of Depressurization Timing on the Thermal Load To Primary Containment Vessel During Severe Accident at BWR
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Topics: Accidents, Boiling water reactors, Containment vessels, Nuclear fission, Thermal loads
Proceedings Papers

Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2

Shotaro Osako, Xin Li, Akifumi Yamaji
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A009, August 8–12, 2022
Paper No: ICONE29-89102
https://doi.org/10.1115/ICONE29-89102
View Paper titled, Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2
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Topics: Accidents, Fuels, Fukushima nuclear disaster, Japan, 2011, Heat, Oxidation, Melting, Temperature, Leakage, Nuclear decommissioning, Nuclear power stations
Journal Articles

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.
Paper No: NERS-21-1135
https://doi.org/10.1115/1.4053827
Published Online: June 15, 2022
View Article titled, Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
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Topics: Design, Vessels, Cycles, Fuels, Temperature, Fast neutron reactors, Small modular reactors
Proceedings Papers

Preliminary Core Design of the Solid Moderator Reactor for Investigation of the In-Depth Europa Ice Layer

Shuta Fukizaki, Akifumi Yamaji, Takanari Fukuda
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A008, August 4–6, 2021
Paper No: ICONE28-64261
https://doi.org/10.1115/ICONE28-64261
View Paper titled, Preliminary Core Design of the Solid Moderator Reactor for Investigation of the In-Depth Europa Ice Layer
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Topics: Design, Ice
Proceedings Papers

Design Study of SMR Class Super FR Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A005, August 4–6, 2021
Paper No: ICONE28-64162
https://doi.org/10.1115/ICONE28-64162
View Paper titled, Design Study of SMR Class Super FR Core for In-Vessel Retention
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Topics: Accidents, Design, Small modular reactors, Supercritical water reactors, Vessels, Water
Proceedings Papers

Preliminary Evaluation on the Relocation Phase of Ex-Vessel Debris of Fukushima Daiichi Nuclear Power Plant Unit-3

Xin Li, Akifumi Yamaji, Masahiro Furuya, Ikken Sato, Hiroshi Madokoro, Yuji Ohishi
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, V003T12A027, August 4–6, 2021
Paper No: ICONE28-64540
https://doi.org/10.1115/ICONE28-64540
View Paper titled, Preliminary Evaluation on the Relocation Phase of Ex-Vessel Debris of Fukushima Daiichi Nuclear Power Plant Unit-3
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Topics: Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Vessels
Proceedings Papers

Analyses of Wet and Dry Cavity Strategies for BWR Severe Accident Management With MELCOR-2.2

Ayato Takashima, Akifumi Yamaji, Xin Li, Daisuke Fujiwara, Hiroshi Shirai, Takumi Noujuu
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, V003T12A006, August 4–6, 2021
Paper No: ICONE28-63285
https://doi.org/10.1115/ICONE28-63285
View Paper titled, Analyses of Wet and Dry Cavity Strategies for BWR Severe Accident Management With MELCOR-2.2
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Topics: Accident management, Accidents, Boiling water reactors, Cavities
Proceedings Papers

Estimation of Long-Term Ex-Vessel Debris Cooling by Water in Fukushima Daiichi Nuclear Power Plant Unit-3

Ikken Sato, Akifumi Yamaji, Xin Li, Hiroshi Madokoro
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, V003T12A016, August 4–6, 2021
Paper No: ICONE28-64246
https://doi.org/10.1115/ICONE28-64246
View Paper titled, Estimation of Long-Term Ex-Vessel Debris Cooling by Water in Fukushima Daiichi Nuclear Power Plant Unit-3
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Topics: Cooling, Floods, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Vessels, Water
Proceedings Papers

Numerical Study of Collision Behavior of Melt Drops During Fuel-Coolant Interaction

Panpan Wen, Gen Li, Jinchen Gao, Yupeng Li, Akifumi Yamaji, Junjie Yan
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A013, August 4–5, 2020
Paper No: ICONE2020-16206
https://doi.org/10.1115/ICONE2020-16206
View Paper titled, Numerical Study of Collision Behavior of Melt Drops During Fuel-Coolant Interaction
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Topics: Collisions (Physics), Computer simulation, Coolants, Drops, Fuels
Proceedings Papers

Preliminary Investigation on Improvement of FP Management During BWR Severe Accident With MELCOR-2.2

Kento Matsubara, Akifumi Yamaji, Xin Li, Daisuke Fujiwara, Hiroshi Shirai, Takumi Noujuu
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A020, August 4–5, 2020
Paper No: ICONE2020-16182
https://doi.org/10.1115/ICONE2020-16182
View Paper titled, Preliminary Investigation on Improvement of FP Management During BWR Severe Accident With MELCOR-2.2
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Topics: Accident management, Accidents, Boiling water reactors
Proceedings Papers

A Core Design of Innovative Breeder BWR

Guo Rui, Akifumi Yamaji, Yun Cai, Xingjie Peng
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A017, July 22–26, 2018
Paper No: ICONE26-82079
https://doi.org/10.1115/ICONE26-82079
View Paper titled, A Core Design of Innovative Breeder BWR
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Topics: Boiling water reactors, Design, Manufacturing, Water, Atoms, Cooling, Fuels, Neutrons, Economics , Heavy metals
Proceedings Papers

Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density

Shogo Noda, Sukarman Sukarman, Akifumi Yamaji, Tetsuo Takei, Takanari Fukuda, Arisa Ayukawa
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A011, July 22–26, 2018
Paper No: ICONE26-81501
https://doi.org/10.1115/ICONE26-81501
View Paper titled, Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density
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Topics: Coolants, Density, Design, Fuels, Breeder reactors, Collisions (Physics), Neutron flux, Neutrons, Probability, Temperature
Proceedings Papers

Three-Dimensional Numerical Study on Pool Stratification Behavior in Molten Corium-Concrete Interaction (MCCI) With MPS Method

Xin Li, Ikken Sato, Akifumi Yamaji, Guangtao Duan
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A023, July 22–26, 2018
Paper No: ICONE26-82037
https://doi.org/10.1115/ICONE26-82037
View Paper titled, Three-Dimensional Numerical Study on Pool Stratification Behavior in Molten Corium-Concrete Interaction (MCCI) With MPS Method
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Topics: Concretes, Ablation (Vaporization technology), Particulate matter, Modeling, Containment, Metals, Accident management, Accidents, Cavities, Computer simulation
Journal Articles

Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water

Sukarman, Akifumi Yamaji, Takayuki Someya
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011012.
Paper No: NERS-17-1033
https://doi.org/10.1115/1.4037719
Published Online: December 4, 2017
View Article titled, Improved Core Design of a High Breeding Fast Reactor Cooled by Supercritical Pressure Light Water
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Topics: Coolants, Design, Fuels, Manufacturing, Pressure, Water, Fast neutron reactors, Power density
Proceedings Papers

Investigation on Accident Progression and Melt Behavior at the Fukushima Daiichi Units 1 and 2 Using MELCOR Code

Gen Li, Shan Zheng, Akifumi Yamaji, Daotong Chong, Junjie Yan
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A029, July 2–6, 2017
Paper No: ICONE25-66389
https://doi.org/10.1115/ICONE25-66389
View Paper titled, Investigation on Accident Progression and Melt Behavior at the Fukushima Daiichi Units 1 and 2 Using MELCOR Code
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Modeling, Failure, Failure mechanisms, Floods, Leakage, Pipes, Pressure, Pressure vessels
Proceedings Papers

Conceptual Core Design of Breeding BWR

Rui Guo, Akifumi Yamaji
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A024, July 2–6, 2017
Paper No: ICONE25-66829
https://doi.org/10.1115/ICONE25-66829
View Paper titled, Conceptual Core Design of Breeding BWR
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Topics: Boiling water reactors, Design, Water, Light water reactors, Fuels, Manufacturing, Neutrons, Atoms, Coolants, Cooling