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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, V001T03A002, August 4–6, 2021

Paper No: ICONE28-63277

DOI: https://doi.org/10.1115/ICONE28-63277

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Topics: Alloys, Corrosion, Corrosion resistance, Iron, Oxygen, Stainless steel, Cancer, Fast neutron reactors, Irradiation (Radiation exposure), Mass production

Proceedings Papers

Analysis and Research on Sodium Single Droplet Combustion

Lei Zhao

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, V003T12A020, August 4–6, 2021

Paper No: ICONE28-64402

DOI: https://doi.org/10.1115/ICONE28-64402

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Topics: Combustion, Drops, Sodium, Fire, Sodium fast reactors, Oxygen, Absorption, Accidents, Chemical properties, Chemical reactions

Proceedings Papers

Modeling of Low-Temperature Reduction of Metal Oxide in Hydrogen Treatment System for Severe Accidents in Nuclear Power Plants

Kotaro Nakamura, Masashi Tanabe, Satoru Abe, Takashi Mawatari, Takao Nakagaki

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A029, August 4–5, 2020

Paper No: ICONE2020-16450

DOI: https://doi.org/10.1115/ICONE2020-16450

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Topics: Accidents, Copper, Hydrogen, Low temperature, Metals, Modeling, Nuclear power stations, Oxidation, Explosions, Water vapor

Proceedings Papers

Numerical Analysis of Single-Phase Thermal Hydraulic Parameters Along Nanostructured Coating Film

Omar S. Al-Yahia, Yacine Addad, Ho Joon Yoon, Sung Oh Cho

Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T03A007, August 4–5, 2020

Paper No: ICONE2020-16316

DOI: https://doi.org/10.1115/ICONE2020-16316

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Topics: Coating processes, Coatings, Numerical analysis, Coolants, Cladding systems (Building), Convection, Fuels, Hydrogen, Chemical processes, Computational fluid dynamics

Proceedings Papers

Numerical Investigation of Mass Mixing in the Reactor Core of a Pebble Bed HTGR

Wei Lu, Xiaowei Li, Xinxin Wu

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A022, July 22–26, 2018

Paper No: ICONE26-81722

DOI: https://doi.org/10.1115/ICONE26-81722

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Topics: Very high temperature reactors, Fuels, Flow (Dynamics), Oxidation, Accidents, Computer simulation, Coolants, Corrosion, Diffusion (Physics), Gases

Proceedings Papers

A Systematic Study of the Material Performance of Hot Isostatically Pressed Type 316L Stainless Steel Powder for the Civil Nuclear Sector

William Kyffin, David Gandy, Barry Burdett

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A017, July 22–26, 2018

Paper No: ICONE26-81438

DOI: https://doi.org/10.1115/ICONE26-81438

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Topics: Stainless steel, Manufacturing, Materials properties, Oxygen, ASTM International, Collaboration, Cycles, Defense industry, Electricity (Physics), Hot pressing

Proceedings Papers

Study on Control Strategy of Hydrogen Risk in Small Containment Under Severe Accident

Zou Zhiqiang, Zhang Ming, Peng Huanhuan, Hou Liqiang, Deng Chunrui, Qiao Xuedong

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A008, July 22–26, 2018

Paper No: ICONE26-81899

DOI: https://doi.org/10.1115/ICONE26-81899

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Topics: Accidents, Containment, Hydrogen, Risk, Oxygen, Steam, Steel, Combustion, Condensation, Cooling systems

Proceedings Papers

A Critical Experimental Study of Bubble Effect in the Process of Spent Fuel Dissolving

Zhou Xiaoping, Liang Shuhong, Xia Zhaodong

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A021, July 22–26, 2018

Paper No: ICONE26-81644

DOI: https://doi.org/10.1115/ICONE26-81644

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Topics: Bubbles, Spent nuclear fuels, Nuclear fuels, Absorption, Fuels, Heat, Leakage, Neutrons, Safety, Simulation

Proceedings Papers

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Yuta Abe, Takuya Yamashita, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi, Yuji Nagae

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A014, July 22–26, 2018

Paper No: ICONE26-81411

DOI: https://doi.org/10.1115/ICONE26-81411

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Topics: Accidents, Fuels, Heating, Manufacturing, Melting, Plasmas (Ionized gases), Blades, Computerized tomography, Electrons, Engineering prototypes

Proceedings Papers

Development of Hydrogen Treatment System in Severe Accident: Part 4 — Study of Fission Products and Steam Effect on Hydrogen Treatment Characteristics

Akira Yamada, Motoshige Yagyu, Chikako Iwaki, Tsukasa Sugita, Yoshiko Haruguchi, Masashi Tanabe

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A024, July 22–26, 2018

Paper No: ICONE26-81759

DOI: https://doi.org/10.1115/ICONE26-81759

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Topics: Accidents, Hydrogen, Nuclear fission, Steam, Vents, Boiling water reactors, Pressure, Manganese dioxide, Metals, Oxidation

Proceedings Papers

Development of Hydrogen Treatment System in Severe Accident: Part 5 — Effect of Steam Flow on Performance of a Hydrogen Treatment Unit With Metal Oxides

Chikako Iwaki, Tsukasa Sugita, Akira Yamada, Motoshige Yagyu, Yoshiko Haruguchi, Masashi Tanabe

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A013, July 22–26, 2018

Paper No: ICONE26-81386

DOI: https://doi.org/10.1115/ICONE26-81386

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Topics: Accidents, Flow (Dynamics), Hydrogen, Metals, Steam, Pipes, Temperature, Boiling water reactors, Containment vessels, Errors

Proceedings Papers

Hydrogen Risk Reducing Technology in Small Modular Reactor

YanLin Chen, XueFeng Lv

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, V001T13A014, July 22–26, 2018

Paper No: ICONE26-81705

DOI: https://doi.org/10.1115/ICONE26-81705

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Topics: Hydrogen, Risk, Small modular reactors, Containment, Accidents, Blasting, Control systems, Domes (Structural elements), Flames, Oxygen

Proceedings Papers

Upgrade and Shakedown Test of a High Temperature Fluoride Salt Test Loop

Xiangbo Kong, Yuan Fu, Jianyu Zhang, Huiju Lu, Naxiu Wang

Paper No: ICONE26-81222

DOI: https://doi.org/10.1115/ICONE26-81222

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Topics: High temperature, Storage tanks, Flow (Dynamics), Heat exchangers, Pipes, Pumps, Temperature, Alloys, Centrifugal pumps, Convection

Proceedings Papers

Operational Impacts and Consequences of Piping Component Failure: A Review of Operating Experience Data As Recorded in CODAP

Braedon Carr, Bengt Lydell, Jovica R. Riznic

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A001, July 22–26, 2018

Paper No: ICONE26-81001

DOI: https://doi.org/10.1115/ICONE26-81001

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Topics: Failure, Pipes, Water, Chemistry, Transients (Dynamics), Accidents, Boiling water reactors, Control systems, Corrosion, Corrosion resistance

Proceedings Papers

Basic Experimental Study on Effectiveness of Nuclear Waste Long-Term Storage Containers With PAR for Reducing Concentration of Hydrogen Gas: Part 2 — Hydrogen Behavior in a Small-Scale Modeled Container

Y. Hiraki, G. Takase, Y. Suzuki, Y. Tanaka, K. Takase

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A047, July 22–26, 2018

Paper No: ICONE26-81704

DOI: https://doi.org/10.1115/ICONE26-81704

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Topics: Containers, Hydrogen, Radioactive wastes, Storage, Fuels, Safety, Steam, Chemical reactions, Computer simulation, Explosions

Proceedings Papers

High Temperature Oxidation of Zry-4 in Oxygen-Nitrogen Atmospheres

Martin Negyesi, Masaki Amaya

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A035, July 2–6, 2017

Paper No: ICONE25-67609

DOI: https://doi.org/10.1115/ICONE25-67609

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Topics: High temperature, Nitrogen, Oxidation, Oxygen, Weight (Mass), Flow (Dynamics), Cladding systems (Building), Compression, Embrittlement, Fuels

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A Modified Two-Zone Model for Predicting Heat Release Rate of Pool Fire in a Confined Space

Research on Compliance Between Large Break LOCA of HPR1000 and New LOCA Acceptance Criterion 10CFR50.46c

First-Principles Study on Adsorption Reaction of Oxygen Molecules on Fe (110) Crystal Surface

Corrosion Behavior of Zr-0.75Sn-0.35Fe-0.15Cr- x Nb Alloys in Oxygen-Containing Super-Heated Steam at 400 °C

Corrosion Behavior of Iron-Chrome Alloys in Liquid Bismuth

Analysis and Research on Sodium Single Droplet Combustion

Modeling of Low-Temperature Reduction of Metal Oxide in Hydrogen Treatment System for Severe Accidents in Nuclear Power Plants

Numerical Analysis of Single-Phase Thermal Hydraulic Parameters Along Nanostructured Coating Film

Numerical Investigation of Mass Mixing in the Reactor Core of a Pebble Bed HTGR

A Systematic Study of the Material Performance of Hot Isostatically Pressed Type 316L Stainless Steel Powder for the Civil Nuclear Sector

Study on Control Strategy of Hydrogen Risk in Small Containment Under Severe Accident

A Critical Experimental Study of Bubble Effect in the Process of Spent Fuel Dissolving

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Development of Hydrogen Treatment System in Severe Accident: Part 4 — Study of Fission Products and Steam Effect on Hydrogen Treatment Characteristics

Development of Hydrogen Treatment System in Severe Accident: Part 5 — Effect of Steam Flow on Performance of a Hydrogen Treatment Unit With Metal Oxides

Hydrogen Risk Reducing Technology in Small Modular Reactor

Upgrade and Shakedown Test of a High Temperature Fluoride Salt Test Loop

Operational Impacts and Consequences of Piping Component Failure: A Review of Operating Experience Data As Recorded in CODAP

Basic Experimental Study on Effectiveness of Nuclear Waste Long-Term Storage Containers With PAR for Reducing Concentration of Hydrogen Gas: Part 2 — Hydrogen Behavior in a Small-Scale Modeled Container

High Temperature Oxidation of Zry-4 in Oxygen-Nitrogen Atmospheres

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