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Proceedings Papers

Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel

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Duan Qianni, Li Wei, Wu Junmei
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A035, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135085
https://doi.org/10.1115/ICONE31-135085
View Paper titled, Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel
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Topics: High cycle fatigue, Nuclear fuels, Neutrons, Physics, Power density, Fuels, Geometry, Innovation, Thermal hydraulics, Uranium
Proceedings Papers

The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme

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Songyang Liu, Xuelin Li, Yong Luo, Wei Liu, Qin Zhou, Cheng Gu, Tian Zhang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133310
https://doi.org/10.1115/ICONE31-133310
View Paper titled, The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme
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Topics: Accidents, Steady state, Fuels, Temperature, China, Equilibrium (Physics), Graphite, Construction, Coolants, Design
Proceedings Papers

JENDL-5 Benchmarking for Advanced Test Reactor for Preparing Burnup Analysis Using Isotopic Data From HTGR Type Fuel Irradiation Tests

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Shoichiro Okita, Takeshi Aoki, Yuji Fukaya, Yukio Tachibana
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131748
https://doi.org/10.1115/ICONE31-131748
View Paper titled, JENDL-5 Benchmarking for Advanced Test Reactor for Preparing Burnup Analysis Using Isotopic Data From HTGR Type Fuel Irradiation Tests
Open the PDF for JENDL-5 Benchmarking for Advanced Test Reactor for Preparing Burnup Analysis Using Isotopic Data From HTGR Type Fuel Irradiation Tests in another window
Topics: Fuels, Irradiation (Radiation exposure), Very high temperature reactors, Heat, Nuclides, Accuracy and precision, Errors, Evaluation methods, Nuclear power, Power density
Proceedings Papers

Study on Thermal-Hydraulic Characteristics of Horizontal Lead-Based Reactor Whole Core

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Minyang Gui, Di Wu, Hangyuan Zhang, Senmiao Zhang, Hui Cheng
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A106, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136580
https://doi.org/10.1115/ICONE31-136580
View Paper titled, Study on Thermal-Hydraulic Characteristics of Horizontal Lead-Based Reactor Whole Core
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Topics: Cladding systems (Building), Coolants, Fast neutron reactors, Flow (Dynamics), Gravity (Force), Manufacturing, Nuclear power stations, Power density, Safety, Temperature
Proceedings Papers

Research on the Applicability of the IWF Model to Coupled Heat Transfer Between Intra- and Inter-Assembly in LFR

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Di Wu, Minyang Gui, Jie Cheng, Jianjun Wang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131238
https://doi.org/10.1115/ICONE31-131238
View Paper titled, Research on the Applicability of the IWF Model to Coupled Heat Transfer Between Intra- and Inter-Assembly in LFR
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Topics: Heat transfer, Manufacturing, Numerical analysis, Safety, Flow (Dynamics), Fluids, Accuracy and precision, Boundary-value problems, Design, Energy generation
Proceedings Papers

Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis

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Zihao Guo, Guang Wang, Genghua Su, Xiuan Shi
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A036, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93256
https://doi.org/10.1115/ICONE29-93256
View Paper titled, Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis
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Topics: Design, Irradiation (Radiation exposure), Neutron flux, Physics, Water, Biomedicine, Isotopes, Cycles, Decontamination, Fuels
Proceedings Papers

Investigation on the Active Learning Optimization on Rotor Dynamics of SCO2 Turbine

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Zhaoli Zheng, Jun Wu, Zhiwu Ke, Zhenxing Zhao, Xiaohu Yang, Lu Dai
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A027, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91731
https://doi.org/10.1115/ICONE29-91731
View Paper titled, Investigation on the Active Learning Optimization on Rotor Dynamics of SCO2 Turbine
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Topics: Optimization, Rotordynamics, Supercritical carbon dioxide, Turbines, Rotors, Brayton cycle, Safety, Separation (Technology), Dynamics (Mechanics), Eigenvalues
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

High Power Electron Beam Dump at DALS

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Kai Tao, Liming Huang, Yadong Ding, Zhenhai Zou, Dejun E
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91515
https://doi.org/10.1115/ICONE29-91515
View Paper titled, High Power Electron Beam Dump at DALS
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Topics: Cathode ray oscilloscopes, Design, Electron beams, Cooling, Radiation (Physics), Water, Aluminum alloys, Fins, Gamma rays, Geometry
Proceedings Papers

Modular Boiling Water Reactor Concept

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Liao Yi, Wang Cong, Chen Lei
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A009, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81196
https://doi.org/10.1115/ICONE26-81196
View Paper titled, Modular Boiling Water Reactor Concept
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Topics: Boiling water reactors, Cycles, Equilibrium (Physics), Blades, Fuels, Manufacturing, Nuclear fuel cycle, Safety, Computer software, Construction
Proceedings Papers

Development of Single Pebble Benchmark Ex. I-2A for IAEA UAM CRP With MOOSE

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Jinlin Niu, Lidong Wang, Jiong Guo, Fu Li
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A033, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82155
https://doi.org/10.1115/ICONE26-82155
View Paper titled, Development of Single Pebble Benchmark Ex. I-2A for IAEA UAM CRP With MOOSE
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Topics: Carbon reinforced plastics, Temperature, Convection, Coolants, Electrical conductivity, Fuels, Helium, Modeling, Power density, Shells
Proceedings Papers

Experimental Nusselt Number in Rod Bundles Cooled by Heavy-Liquid Metals

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J. Pacio, M. Daubner, T. Wetzel, I. Di Piazza, M. Tarantino, D. Martelli, M. Angelucci
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A041, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82213
https://doi.org/10.1115/ICONE26-82213
View Paper titled, Experimental Nusselt Number in Rod Bundles Cooled by Heavy-Liquid Metals
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Topics: Fuel rods, Metals, Flow (Dynamics), Fuels, Temperature, Coolants, Heat transfer, Thermocouples, Wire, Computer simulation
Proceedings Papers

Thermal-Hydraulic Analysis of TOPAZ-II With Modified RELAP5

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Simiao Tang, Chenglong Wang, G. H. Su, Suizheng Qiu, Wenxi Tian
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A068, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81735
https://doi.org/10.1115/ICONE26-81735
View Paper titled, Thermal-Hydraulic Analysis of TOPAZ-II With Modified RELAP5
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Topics: Accidents, Automatic control, Boiling, Coolants, Feedback, Fuels, Heat transfer, Liquid metals, Melting, Neutrons
Proceedings Papers

Design and Non-Proliferation Viability of Small Modular Reactors

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Zafar ullah Koreshi
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, V001T13A013, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81651
https://doi.org/10.1115/ICONE26-81651
View Paper titled, Design and Non-Proliferation Viability of Small Modular Reactors
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Topics: Design, Small modular reactors, Nuclear power, Carbon, Emissions, Nuclear reactors, Power density, Risk, Safety, Signals
Proceedings Papers

Numerical Study on the Two-Phase Flow for a Gas/Liquid Metal Magnetohydrodynamic Generator

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Meng-Ran Liao, Chun-Hui Dai, Can Ma, Yong Liu, Zheng-Xing Zhao, Zhou-Yang 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, V001T13A018, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82231
https://doi.org/10.1115/ICONE26-82231
View Paper titled, Numerical Study on the Two-Phase Flow for a Gas/Liquid Metal Magnetohydrodynamic Generator
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Topics: Generators, Liquid metals, Magnetohydrodynamics, Two-phase flow, Fluids, Porosity, Temperature, Bubbles, Cycles, Dimensions
Proceedings Papers

Moving From V&V to V&V&C in Nuclear Thermal-Hydraulics

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Francesco D’Auria, Marco Lanfredini
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82574
https://doi.org/10.1115/ICONE26-82574
View Paper titled, Moving From V&V to V&V&C in Nuclear Thermal-Hydraulics
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Topics: Density, Film boiling, Flow (Dynamics), Heat flux, High pressure (Physics), Nucleate boiling, Pipes, Power density, Pressure, Temperature
Proceedings Papers

Piezoelectric Nuclear Battery Driven by the Jet-Flow

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Y. Zhou, S. X. Zhang, G. P. Li
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A030, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66981
https://doi.org/10.1115/ICONE25-66981
View Paper titled, Piezoelectric Nuclear Battery Driven by the Jet-Flow
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Topics: Atomic batteries, Jets, Radioisotopes, Batteries, Brayton cycle, Energy conversion, Energy resources, Flow (Dynamics), Fuels, Half-life
Proceedings Papers

A Novel High-Power Magnetic Transmission System Based on Magnetic Conductivity Modulation Principle

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Mo Tao, Jun Wu, Zhiwu Ke, Xianling Li, Yong Li
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A116, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67959
https://doi.org/10.1115/ICONE25-67959
View Paper titled, A Novel High-Power Magnetic Transmission System Based on Magnetic Conductivity Modulation Principle
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Topics: Electrical conductivity, Thermal conductivity, Torque, Permanent magnets, Rotors, Vibration, Deformation, Density, Gears, Nuclear power
Proceedings Papers

Modeling and Thermal Calculation of Fuel Rod With SiC f /SiC Cladding for LWRs

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Shang Xinyuan, Zhang Shaoyang, Zhang Aimin
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A040, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67078
https://doi.org/10.1115/ICONE25-67078
View Paper titled, Modeling and Thermal Calculation of Fuel Rod With SiC f /SiC Cladding for LWRs
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Topics: Cladding systems (Building), Fuel rods, Light water reactors, Modeling, Fuels, Composite materials, Design, Fibers, Fluence (Radiation measurement), Neutrons
Proceedings Papers

Analysis and Prospect of the Duplex Fuel Pellets of LOWI Type for Water-Cooled Reactors

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Songyang Li, Dingqu Wang, Wenli Guo, Yueyuan Jiang
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A021, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60505
https://doi.org/10.1115/ICONE24-60505
View Paper titled, Analysis and Prospect of the Duplex Fuel Pellets of LOWI Type for Water-Cooled Reactors
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Topics: Fuels, Water, Design, Manufacturing, Nuclear fuels, Power density, Temperature, Annulus, Cutting, Geometry