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Proceedings Papers

High-Order Harmonics Calculation for the Power Reconstruction of 3D Pin-Scale Whole-Core

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Zhinan Xie, Chen Hao, Wen Yin
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A061, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136320
https://doi.org/10.1115/ICONE31-136320
View Paper titled, High-Order Harmonics Calculation for the Power Reconstruction of 3D Pin-Scale Whole-Core
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Topics: Diffusion (Physics), Heating, Low temperature, Manufacturing, Neutrons
Proceedings Papers

Effect of Geometric Parameters on Cooling Performance of The Concrete Shielding for Swimming Pool-Type Low-Temperature Heating Reactor

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Guangming Fan, Shuai Hao, Zongkun Li, Jiaming Li, Shicong Guan
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134626
https://doi.org/10.1115/ICONE31-134626
View Paper titled, Effect of Geometric Parameters on Cooling Performance of The Concrete Shielding for Swimming Pool-Type Low-Temperature Heating Reactor
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Topics: Concretes, Cooling, Heating, Low temperature
Proceedings Papers

Experimental Study on the Sealing Performance of Core Barrel Flange for Swimming Pool-Type Low-Temperature Heating Reactor

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Song Yu, Weiming Zhai, Daoxi Cheng, Ping Zhou, Xiaoyao Ma, Ruizhi Li, Mingdi Xing, Weilong Gao
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A053, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134990
https://doi.org/10.1115/ICONE31-134990
View Paper titled, Experimental Study on the Sealing Performance of Core Barrel Flange for Swimming Pool-Type Low-Temperature Heating Reactor
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Topics: Flanges, Heating, Leakage, Low temperature, Sealing (Process)
Proceedings Papers

Experimental Studies on Two-Layer Stratified Molten Pool Heat Transfer With Water and 1-Octanol

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Fengyang Quan, Jie Pei, Wei Li, Yidan Yuan
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A014, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136323
https://doi.org/10.1115/ICONE31-136323
View Paper titled, Experimental Studies on Two-Layer Stratified Molten Pool Heat Transfer With Water and 1-Octanol
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Topics: Accidents, Heat transfer, Water, High temperature, Low temperature, Rayleigh number, China, Heat, Nuclear engineering, Reliability
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92285
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92795
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

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90835
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

Research of a Fast Sample Preparation Method for Water Radioactivity Measurement

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-60437
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

A Finnish District Heating Reactor: Background and General Overview

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64346
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

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16450
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

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16109
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

Experimental and Modeling Research on Leading Betavoltaic Technology

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82475
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82006
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

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

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Ahmed Aly, Victor Petrov, Maria Avramova, Annalisa Manera, Kostadin Ivanov
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A087, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82431
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

Status of District Heating Reactor and its Development Prospects in China

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82445
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

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66189
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

Flow Field Analysis of the Reactor Coolant Pump Internal Cooling Circulation

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67179
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

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67054
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67876
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

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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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67627
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