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Proceedings Papers

Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines

Yifeng Hu, Zhiqiang Hu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A013, August 8–12, 2022
Paper No: ICONE29-91474
DOI: https://doi.org/10.1115/ICONE29-91474
View Paper titled, Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines
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Topics: Design, Pareto optimization, Turbines, Stress, Deformation, Optimization, Steam turbines, Design methodology, Weight (Mass), Buckling
Proceedings Papers

Preliminary Study on Three-Dimensional Characteristics of Modular High Temperature Gas-Cooled Reactor

Haojie Zhang, Yanhua Zheng, Ding She, Lei Shi
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A057, August 8–12, 2022
Paper No: ICONE29-91754
DOI: https://doi.org/10.1115/ICONE29-91754
View Paper titled, Preliminary Study on Three-Dimensional Characteristics of Modular High Temperature Gas-Cooled Reactor
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Topics: Rods, Very high temperature reactors
Proceedings Papers

Determination of Control Rod Position by Global Optimization Methods

Zhang Qian, Zhihong Liu, Jing Zhao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A100, August 8–12, 2022
Paper No: ICONE29-92637
DOI: https://doi.org/10.1115/ICONE29-92637
View Paper titled, Determination of Control Rod Position by Global Optimization Methods
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Topics: Algorithms, Optimization, Pressurized water reactors, Sensors, Computer software, Genetic algorithms, Inverse problems, Neutrons, Particle swarm optimization, Physics
Proceedings Papers

A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs

Pengtao Fu, Zhijun Li
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A063, August 8–12, 2022
Paper No: ICONE29-92788
DOI: https://doi.org/10.1115/ICONE29-92788
View Paper titled, A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs
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Topics: Failure, Fuel rods, Fuels, Nuclear fission, Pressurized water reactors, Cladding systems (Building), Rods, Irradiation (Radiation exposure)
Proceedings Papers

Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods

Wei Li, Jianfeng Shi, Yulong Qin, Lihua Wang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A047, August 8–12, 2022
Paper No: ICONE29-92633
DOI: https://doi.org/10.1115/ICONE29-92633
View Paper titled, Research on Technical Scheme of Rapid Power Reduction System Based on Gray Control Rods
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Topics: Feedwater, Pumps, Rods, Nuclear power stations, Turbines
Proceedings Papers

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Yaoxin Ye, Pengtao Fu, Zhijun Li
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 8–12, 2022
Paper No: ICONE29-89461
DOI: https://doi.org/10.1115/ICONE29-89461
View Paper titled, Research on the Influence of Degassing on the Release of Fission Gases in PWRs
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Topics: Failure, Fuels, Gases, Nuclear fission, Pressurized water reactors, Coolants, Nuclear power stations, Cladding systems (Building), Nuclear fuel cycle, Rods
Proceedings Papers

Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

Zhipeng Lv, Guoliang Zhang, Changzheng Li, Weichao Liu, Shaofang Lin, Lihong Nie, Zhijun Li, Anlong Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A067, August 8–12, 2022
Paper No: ICONE29-93095
DOI: https://doi.org/10.1115/ICONE29-93095
View Paper titled, Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures
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Topics: Absorption, Cladding systems (Building), Deformation, Design, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Rods, Safety, Shock absorbers
Proceedings Papers

Application of the Refinement Spacer Grid Model in Subchannel Analysis Code

Si Ying Dong, Ping Yang, Fujun Gan, Yuanrong Liu
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A025, August 8–12, 2022
Paper No: ICONE29-90296
DOI: https://doi.org/10.1115/ICONE29-90296
View Paper titled, Application of the Refinement Spacer Grid Model in Subchannel Analysis Code
Click here to open pdf in another window PDF for Application of the Refinement Spacer Grid Model in Subchannel Analysis Code
Topics: Axial flow, Economics , Flow (Dynamics), Fluids, Friction, Fuel rods, Momentum, Particulate matter, Pressurized water reactors, Rods
Proceedings Papers

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Kaiyuan Wang, Xiaohan Liu, Xin Jin
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A021, August 8–12, 2022
Paper No: ICONE29-89917
DOI: https://doi.org/10.1115/ICONE29-89917
View Paper titled, Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod
Click here to open pdf in another window PDF for Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod
Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission
Proceedings Papers

Alternative Absorber Materials for Control Rods in ALFRED

Hui Guo, Xin Jin, Kuaiyuan Feng, Hanyang Gu
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, V001T03A001, August 4–6, 2021
Paper No: ICONE28-61123
DOI: https://doi.org/10.1115/ICONE28-61123
View Paper titled, Alternative Absorber Materials for Control Rods in ALFRED
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Topics: Fast neutron reactors, Rods
Proceedings Papers

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Jaakko Leppänen, Ville Valtavirta, Riku Tuominen, Antti Rintala, Unna Lauranto
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, V001T04A010, August 4–6, 2021
Paper No: ICONE28-64347
DOI: https://doi.org/10.1115/ICONE28-64347
View Paper titled, A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations
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Topics: Central heating, Design, Engineering simulation, Nuclear fuel cycle, Simulation, Fuels, Boron, Cycles, Heating, Operating temperature
Proceedings Papers

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021
Paper No: ICONE28-66591
DOI: https://doi.org/10.1115/ICONE28-66591
View Paper titled, Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development
Click here to open pdf in another window PDF for Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development
Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux
Proceedings Papers

High-Energy X-Ray CT Measurement of Void Fraction Distribution Around Part Length Rods in a Rod Bundle at High Pressure and Temperatures

Takahiro Arai, Atsushi Ui, Masahiro Furuya, Riichiro Okawa, Tsugumasa Iiyama, Shota Ueda, Kenetsu Shirakawa, Kazuaki Kito
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A042, August 4–5, 2020
Paper No: ICONE2020-16759
DOI: https://doi.org/10.1115/ICONE2020-16759
View Paper titled, High-Energy X-Ray CT Measurement of Void Fraction Distribution Around Part Length Rods in a Rod Bundle at High Pressure and Temperatures
Click here to open pdf in another window PDF for High-Energy X-Ray CT Measurement of Void Fraction Distribution Around Part Length Rods in a Rod Bundle at High Pressure and Temperatures
Topics: Boiling, Computerized tomography, Fuel rods, High pressure (Physics), Porosity, Rods, Temperature, Two-phase flow
Proceedings Papers

Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications

Jeff Ridgway, Bryant Slater
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A058, August 4–5, 2020
Paper No: ICONE2020-16810
DOI: https://doi.org/10.1115/ICONE2020-16810
View Paper titled, Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications
Click here to open pdf in another window PDF for Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications
Topics: Fluids, Gravity (Force), Sensors, Vessels, Leakage, Nuclear power, Sensor placement, Simulation, Accuracy and precision, Algorithms
Proceedings Papers

Multi-Group Staggered Tests for Highly Redundant Systems

Shota Soga
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A002, August 4–5, 2020
Paper No: ICONE2020-16172
DOI: https://doi.org/10.1115/ICONE2020-16172
View Paper titled, Multi-Group Staggered Tests for Highly Redundant Systems
Click here to open pdf in another window PDF for Multi-Group Staggered Tests for Highly Redundant Systems
Topics: Boiling water reactors, Failure, Notch testing, Reactor protection systems, Redundancy (Engineering), Reliability, Risk, Rods, Safety
Proceedings Papers

Development of Numerical Simulation Method to Evaluate Molten Material Behaviors in Nuclear Reactors: Estimation of Fuel Debris Distribution in the Pedestal

Susumu Yamashita, Hiroyuki Yoshida
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A033, July 22–26, 2018
Paper No: ICONE26-82088
DOI: https://doi.org/10.1115/ICONE26-82088
View Paper titled, Development of Numerical Simulation Method to Evaluate Molten Material Behaviors in Nuclear Reactors: Estimation of Fuel Debris Distribution in the Pedestal
Click here to open pdf in another window PDF for Development of Numerical Simulation Method to Evaluate Molten Material Behaviors in Nuclear Reactors: Estimation of Fuel Debris Distribution in the Pedestal
Topics: Computer simulation, Fuels, Nuclear reactors, Accidents, Melting, Alpha decay, Cladding systems (Building), Computational fluid dynamics, Fukushima nuclear disaster, Japan, 2011, Heat
Proceedings Papers

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

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
Paper No: ICONE26-82213
DOI: https://doi.org/10.1115/ICONE26-82213
View Paper titled, Experimental Nusselt Number in Rod Bundles Cooled by Heavy-Liquid Metals
Click here to open pdf in another window PDF for Experimental Nusselt Number in Rod Bundles Cooled by Heavy-Liquid Metals
Topics: Fuel rods, Metals, Flow (Dynamics), Fuels, Temperature, Coolants, Heat transfer, Thermocouples, Wire, Computer simulation
Proceedings Papers

Experimental Activities on Thermal Hydraulics of Heavy Liquid Metal Flow in Typical Elements of Nuclear Power Stations

O. Kashinsky, A. Kurdyumov, P. Lobanov, A. Svetonosov, M. Vorobyev, N. Pribaturin
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A055, July 22–26, 2018
Paper No: ICONE26-82407
DOI: https://doi.org/10.1115/ICONE26-82407
View Paper titled, Experimental Activities on Thermal Hydraulics of Heavy Liquid Metal Flow in Typical Elements of Nuclear Power Stations
Click here to open pdf in another window PDF for Experimental Activities on Thermal Hydraulics of Heavy Liquid Metal Flow in Typical Elements of Nuclear Power Stations
Topics: Flow (Dynamics), Liquid metals, Nuclear power stations, Thermal hydraulics, Coolants, Temperature, Junctions, Rods, Manufacturing, Computational fluid dynamics
Proceedings Papers

A PSA Case Study: Promoting the Reliability of the CRSS on the CMRR Through the ATWS Mitigation System

Heng Yu, Guan-bo Wang, Da-zhi Qian, Yu-chuan Guo, Bo Hu
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A011, July 22–26, 2018
Paper No: ICONE26-81755
DOI: https://doi.org/10.1115/ICONE26-81755
View Paper titled, A PSA Case Study: Promoting the Reliability of the CRSS on the CMRR Through the ATWS Mitigation System
Click here to open pdf in another window PDF for A PSA Case Study: Promoting the Reliability of the CRSS on the CMRR Through the ATWS Mitigation System
Topics: Reliability, Safety, China, Damage, Design, Failure, Probability, Rods, Scram, Transients (Dynamics)
Proceedings Papers

Experimental Study on Flow Instability During Gravity-Driven Reflooding

Lili Tong, Dandi Zhang, Liqiang Hou, Xiaoji Wang
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A005, July 22–26, 2018
Paper No: ICONE26-81736
DOI: https://doi.org/10.1115/ICONE26-81736
View Paper titled, Experimental Study on Flow Instability During Gravity-Driven Reflooding
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Topics: Flow instability, Gravity (Force), Cooling, Steam, Pressure, Water, Accidents, Condensed matter, Coolants, Cylinders