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Proceedings Papers

The Wear and General Corrosion Properties of Low-Temperature Plasma Nitrided 17-4PH Stainless Steel With a Work-Hardened Sublayer

Zhongli Han, Ping Lai, Wenhua Zhuang, Xianglong Guo, Lefu Zhang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A026, August 8–12, 2022
Paper No: ICONE29-90835
DOI: https://doi.org/10.1115/ICONE29-90835
View Paper titled, The Wear and General Corrosion Properties of Low-Temperature Plasma Nitrided 17-4PH Stainless Steel With a Work-Hardened Sublayer
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Topics: Corrosion, Low temperature, Nitriding, Plasmas (Ionized gases), Stainless steel, Wear
Proceedings Papers

Investigation of Swelling Behaviors of U-10Zr Metallic Fuel in the Low Temperature Regime via a Combined Thermo-Mechanical and Rate Theory Analysis

Zhengyu Qian, Di Yun
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A053, August 8–12, 2022
Paper No: ICONE29-92285
DOI: https://doi.org/10.1115/ICONE29-92285
View Paper titled, Investigation of Swelling Behaviors of U-10Zr Metallic Fuel in the Low Temperature Regime via a Combined Thermo-Mechanical and Rate Theory Analysis
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Topics: Fuels, Low temperature, Thermomechanics, Uranium, Zirconium
Proceedings Papers

Development and Verification of Thermal-Hydraulic Constitutive Model for Rectangular Channel

Yun Fei Feng, Lei Li, Ya Jie Nie, Xin Jiao, Jian Yi Li, Si Jia Meng, Ying Hao Li
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A026, August 8–12, 2022
Paper No: ICONE29-92795
DOI: https://doi.org/10.1115/ICONE29-92795
View Paper titled, Development and Verification of Thermal-Hydraulic Constitutive Model for Rectangular Channel
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Topics: Accidents, Constitutive equations, Critical heat flux, Flow (Dynamics), Fuels, Heart failure, Heat transfer, Heat transfer coefficients, Low temperature, Nuclear reactors
Proceedings Papers

A Finnish District Heating Reactor: Background and General Overview

Jaakko Leppänen, Seppo Hillberg, Ville Hovi, Rebekka Komu, Joona Kurki, Unna Lauranto, Ahti Oinonen, Jussi Peltonen, Antti Rintala, Ville Tulkki, Riku Tuominen, Ville Valtavirta
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, V001T04A009, August 4–6, 2021
Paper No: ICONE28-64346
DOI: https://doi.org/10.1115/ICONE28-64346
View Paper titled, A Finnish District Heating Reactor: Background and General Overview
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Topics: Central heating, Design, Coal, Governments, Heat, Boilers, Carbon, Climate, Containment, Energy generation
Proceedings Papers

Research of a Fast Sample Preparation Method for Water Radioactivity Measurement

Shuijun He, Xiangwei Wang, Manchun Liang, Guofeng Su, Anying Chen, Chao Zhang, Ke Li
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, V003T11A003, August 4–6, 2021
Paper No: ICONE28-60437
DOI: https://doi.org/10.1115/ICONE28-60437
View Paper titled, Research of a Fast Sample Preparation Method for Water Radioactivity Measurement
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Topics: Radiation measurement, Water, Boiling, Emergencies, Low temperature, Nuclides, Radioactivity, Radioisotopes, Vacuum
Proceedings Papers

Experimental Study on Natural Convection Heat Transfer Outside Tube Bundle in Space Under Low Temperature Difference

Junxiu Xu, Ming Ding, Changqi Yan, Guangming Fan
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A007, August 4–5, 2020
Paper No: ICONE2020-16109
DOI: https://doi.org/10.1115/ICONE2020-16109
View Paper titled, Experimental Study on Natural Convection Heat Transfer Outside Tube Bundle in Space Under Low Temperature Difference
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Topics: Heat transfer, Low temperature, Natural convection
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
View Paper titled, Modeling of Low-Temperature Reduction of Metal Oxide in Hydrogen Treatment System for Severe Accidents in Nuclear Power Plants
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Topics: Accidents, Copper, Hydrogen, Low temperature, Metals, Modeling, Nuclear power stations, Oxidation, Explosions, Water vapor
Proceedings Papers

Status of District Heating Reactor and its Development Prospects in China

Jing Zhao, Fei Xie, Zhihong Liu
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, V001T13A024, July 22–26, 2018
Paper No: ICONE26-82445
DOI: https://doi.org/10.1115/ICONE26-82445
View Paper titled, Status of District Heating Reactor and its Development Prospects in China
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Topics: Central heating, China, Heating, Low temperature, Construction, Design, Heat, Nuclear power, Nuclear reactors, Power stations
Proceedings Papers

Evaluation of the Mixing Vanes Effect on the Hydrogen Diffusion and Hydride Formation in the Fuel Cladding

Ahmed Aly, Victor Petrov, Maria Avramova, Annalisa Manera, Kostadin Ivanov
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A087, July 22–26, 2018
Paper No: ICONE26-82431
DOI: https://doi.org/10.1115/ICONE26-82431
View Paper titled, Evaluation of the Mixing Vanes Effect on the Hydrogen Diffusion and Hydride Formation in the Fuel Cladding
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Topics: Cladding systems (Building), Diffusion (Physics), Fuels, Hydrogen, Coolants, Fuel rods, Temperature gradient, Temperature profiles, Water, Boundary-value problems
Proceedings Papers

Experimental and Modeling Research on Leading Betavoltaic Technology

Thomas E. Adams, Shripad T. Revankar, Darrell S. Cheu, Peter Cabauy, Jesse Grant, Bret Elkind
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A056, July 22–26, 2018
Paper No: ICONE26-82475
DOI: https://doi.org/10.1115/ICONE26-82475
View Paper titled, Experimental and Modeling Research on Leading Betavoltaic Technology
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Topics: Modeling, Electrolytes, Leakage, Temperature, Corrosion, Defense industry, Electronics, Explosions, Fire, Hazards
Proceedings Papers

Qualification Test of APR1400’s RCP Seal Under Extended SBO Condition

Seok Cho, Seok Kim, Byoung-Uhn Bae, Yun-Je Cho, Yeon-Sik Kim, Woo-Jin Jeon, Young-Jung Youn, Sung-Min Chu, Sang-Youn Bang
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A017, July 22–26, 2018
Paper No: ICONE26-82006
DOI: https://doi.org/10.1115/ICONE26-82006
View Paper titled, Qualification Test of APR1400’s RCP Seal Under Extended SBO Condition
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Topics: Construction, Engines, Fukushima nuclear disaster, Japan, 2011, High pressure (Physics), High temperature, Impellers, Leakage, Leakage flows, Low temperature, Manufacturing
Proceedings Papers

Experiment and Numerical Analysis of Mixing Process of Two Component Gases in Vertical Fluid Layer

Tetsuaki Takeda
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A111, July 2–6, 2017
Paper No: ICONE25-67750
DOI: https://doi.org/10.1115/ICONE25-67750
View Paper titled, Experiment and Numerical Analysis of Mixing Process of Two Component Gases in Vertical Fluid Layer
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Topics: Fluids, Gases, Numerical analysis, Accidents, Natural convection, Very high temperature reactors, Diffusion (Physics), Flow (Dynamics), High temperature, Storage tanks
Proceedings Papers

Setup of the Supercritical CO2 Test-Facility “Scarlett” for Basic Experimental Investigations of a Compact Heat Exchanger for an Innovative Decay Heat Removal System

Wolfgang Flaig, Rainer Mertz, Jörg Starflinger
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A098, July 2–6, 2017
Paper No: ICONE25-67519
DOI: https://doi.org/10.1115/ICONE25-67519
View Paper titled, Setup of the Supercritical CO2 Test-Facility “Scarlett” for Basic Experimental Investigations of a Compact Heat Exchanger for an Innovative Decay Heat Removal System
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Topics: Heat, Heat exchangers, Supercritical carbon dioxide, Test facilities, Heat transfer, Pressure, Carbon dioxide, Compressors, Fluids, Nuclear power stations
Proceedings Papers

In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches

Pei Shen, Wenzhong Zhou
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A017, July 2–6, 2017
Paper No: ICONE25-67176
DOI: https://doi.org/10.1115/ICONE25-67176
View Paper titled, In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches
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Topics: Experimental methods, Explosions, Steam, Vessels, Coolants, Heat transfer, Reactor vessels, Accident management, Accidents, Containment
Proceedings Papers

Study on Forging Cracks and Manufacturing Process of 022Cr19Ni10N Austenitic Stainless Steel Rod Travel Housing Forging for Control Rod Drive Mechanism

Chen Mei-fang, Cao Sheng-qiang, Tao Zhi-yong
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A093, July 2–6, 2017
Paper No: ICONE25-67286
DOI: https://doi.org/10.1115/ICONE25-67286
View Paper titled, Study on Forging Cracks and Manufacturing Process of 022Cr19Ni10N Austenitic Stainless Steel Rod Travel Housing Forging for Control Rod Drive Mechanism
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Topics: Forging, Fracture (Materials), Manufacturing, Stainless steel, Ferrites (Magnetic materials), Grain size, Low temperature, Temperature, Nitrogen, Plasticity
Proceedings Papers

Study on Effects of Environment Conditions on Essential Service Water System of Nuclear Power Station

Yang Ting, Li Guang Sheng, Li Zeng Fen, Peng Yue, Hu Jian
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A019, July 2–6, 2017
Paper No: ICONE25-66189
DOI: https://doi.org/10.1115/ICONE25-66189
View Paper titled, Study on Effects of Environment Conditions on Essential Service Water System of Nuclear Power Station
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Topics: Nuclear power stations, Water, Cooling, Economics , Safety, Construction, Design, Failure, Heat sinks, Reservoirs
Proceedings Papers

Annealing Temperature Effect on Creep Property of CZ Alloy for PWR Modern Fuel Claddings

Yang Xu, Jun Tan, Liu-tao Chen, Dun-gu Wen, Hong Zou, Chang-yuan Gao, Xu Wang, Si-si Dong, Wei-jun Wang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A039, July 2–6, 2017
Paper No: ICONE25-67054
DOI: https://doi.org/10.1115/ICONE25-67054
View Paper titled, Annealing Temperature Effect on Creep Property of CZ Alloy for PWR Modern Fuel Claddings
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Topics: Alloys, Annealing, Creep, Fuels, Pressurized water reactors, Temperature, Zirconium alloys, Stress, China, Cladding systems (Building)
Proceedings Papers

Development of Numerical Estimation Method Using Spatial Connection Methodology for Thermal Striping in Upper Plenum of Reactor Vessel of an Advanced Loop-Type Sodium-Cooled Fast Reactor in Japan

Masaaki Tanaka, Satoshi Murakami
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A055, July 2–6, 2017
Paper No: ICONE25-67876
DOI: https://doi.org/10.1115/ICONE25-67876
View Paper titled, Development of Numerical Estimation Method Using Spatial Connection Methodology for Thermal Striping in Upper Plenum of Reactor Vessel of an Advanced Loop-Type Sodium-Cooled Fast Reactor in Japan
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Topics: Reactor vessels, Sodium fast reactors, Flow (Dynamics), Computer simulation, Fuels, Sodium, Fluids, High temperature, Instrumentation, Low temperature
Proceedings Papers

Flow Field Analysis of the Reactor Coolant Pump Internal Cooling Circulation

Jie Qin, Qingmu Xu, Junkai Yuan, Kun Cai
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A040, July 2–6, 2017
Paper No: ICONE25-67179
DOI: https://doi.org/10.1115/ICONE25-67179
View Paper titled, Flow Field Analysis of the Reactor Coolant Pump Internal Cooling Circulation
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Topics: Cooling, Flow (Dynamics), Nuclear reactor coolants, Pumps, Bearings, Engines, Motors, Flywheels, Heat, Heat transfer
Proceedings Papers

Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazard of Low Temperature and Snow for Sodium-Cooled Fast Reactors

Hiroyuki Nishino, Hidemasa Yamano, Kenichi Kurisaka
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T14A038, July 2–6, 2017
Paper No: ICONE25-67627
DOI: https://doi.org/10.1115/ICONE25-67627
View Paper titled, Development of Probabilistic Risk Assessment Methodology of Decay Heat Removal Function Against Combination Hazard of Low Temperature and Snow for Sodium-Cooled Fast Reactors
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Topics: Hazards, Heat, Low temperature, Probabilistic risk assessment, Sodium fast reactors, Failure, Probability, Damage, Filters, Accidents