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Proceedings Papers

Measurement of Gas-Liquid Interfacial Area Concentration and Its Effect on Aerosol Behavior in Pool Scrubbing

Sasuke Kadoma, Kota Fujiwara, Kohei Yoshida, Akiko Kaneko
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A025, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90448
https://doi.org/10.1115/ICONE29-90448
View Paper titled, Measurement of Gas-Liquid Interfacial Area Concentration and Its Effect on Aerosol Behavior in Pool Scrubbing
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Topics: Accidents, Aerosols, Bubbles, Countermeasures, Decontamination, Flow (Dynamics), Nozzles, Nuclear fission, Nuclear power stations, Porosity
Proceedings Papers

Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement

Kai Tan, Ruihan Li, Jian Li, Jingang Liang, Ding She
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A053, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91659
https://doi.org/10.1115/ICONE29-91659
View Paper titled, Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement
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Topics: Nuclides, Pressurized water reactors, Spent nuclear fuels, Density, Errors, Accuracy and precision, Fuels, Heat, Isotopes, Nuclear fission
Proceedings Papers

Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium

Ziling Zhou, Yu Wang, Jingni Guo, Feng Xie, Wenqian Li, Yanwei Wen, Bin Shan
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A039, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91275
https://doi.org/10.1115/ICONE29-91275
View Paper titled, Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium
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Topics: Hydraulic conductivity, Very high temperature reactors, Fusion reactors, Hydrogen, Isotopes, Nuclear reactors, Coolants, Design, Diffusion (Physics), Engineering systems and industry applications
Proceedings Papers

Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6

Chang Zhang, Ruixiang Wang, Hui Guo, Hanyang Gu, Yao Xiao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A101, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92642
https://doi.org/10.1115/ICONE29-92642
View Paper titled, Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6
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Topics: Physics, Thermal hydraulics, Fuels, Temperature, Coolants, Light water reactors, Manufacturing, Simulation, Eigenvalues, Fuel rods
Proceedings Papers

Validation of TULIP via ICSBEP Critical Benchmark

Wenjie Chen, Xianan Du, Youqi Zheng, Yongping Wang, Rong Wang, Hongchun Wu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A113, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93353
https://doi.org/10.1115/ICONE29-93353
View Paper titled, Validation of TULIP via ICSBEP Critical Benchmark
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Topics: Computational physics, Cross section (Physics), Design, Doppler effect, Feedback, Manufacturing, Neutrons, Nuclear design, Nuclear engineering, Nuclear fission
Proceedings Papers

Fission Gas Release Grain Boundary Network Percolation Mechanistic Studies in Oxide Fuels Based on COMSOL Multiphysics Framework

Jingyu Guo, Wenzhong Zhou
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A061, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92732
https://doi.org/10.1115/ICONE29-92732
View Paper titled, Fission Gas Release Grain Boundary Network Percolation Mechanistic Studies in Oxide Fuels Based on COMSOL Multiphysics Framework
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Topics: Fuels, Grain boundaries, Nuclear fission, Percolation theory
Proceedings Papers

Neutronics Analysis of RBMK-1000 Reactor Using OpenMC: Criticality and Depletion Analysis at 3D Assembly Level

Mohammad Hashemi, Rafael Macián-Juan, Martin Ohlerich
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A018, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90636
https://doi.org/10.1115/ICONE29-90636
View Paper titled, Neutronics Analysis of RBMK-1000 Reactor Using OpenMC: Criticality and Depletion Analysis at 3D Assembly Level
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Topics: Manufacturing, Nuclear fission, Spent nuclear fuels, Chemical kinetics, Computer programming languages, Databases, Design, Nuclear power, Nuclear power stations, Parametric design
Proceedings Papers

Research on the Correlations of Fission Source Distribution in the Monte Carlo Algorithm Using Mathematical Tools

Pengfei Shen, Shihang Jiang, Yingzhe Hu, Kan Wang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A081, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93476
https://doi.org/10.1115/ICONE29-93476
View Paper titled, Research on the Correlations of Fission Source Distribution in the Monte Carlo Algorithm Using Mathematical Tools
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Topics: Algorithms, Cycles, Nuclear fission
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92788
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

The Applicability Analysis of Fusion Reactors and China Nuclear Safety Code HAF102

Yijie Qian, Chong Li
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91692
https://doi.org/10.1115/ICONE29-91692
View Paper titled, The Applicability Analysis of Fusion Reactors and China Nuclear Safety Code HAF102
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Topics: China, Fusion reactors, Safety, Design, Defense industry, Nuclear design, Nuclear fission, Nuclear fusion, Nuclear reactors, Regulations
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89917
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
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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission
Proceedings Papers

Three-Dimensional Numerical Simulation of the Release and Migration Behavior of Fission Gas Bubbles in Advanced Reactor Pool Under Serious Accident

Zijun Mai, Zichen Zhao, Hui Cheng, Songbai Cheng
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91240
https://doi.org/10.1115/ICONE29-91240
View Paper titled, Three-Dimensional Numerical Simulation of the Release and Migration Behavior of Fission Gas Bubbles in Advanced Reactor Pool Under Serious Accident
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Topics: Accidents, Bubbles, Computer simulation, Nuclear fission, Engineering simulation, Simulation, Water, Bifurcation, Design, Eutectic alloys
Proceedings Papers

Evaluation of Effect of Depressurization Timing on the Thermal Load To Primary Containment Vessel During Severe Accident at BWR

Taisei Matsumoto, Akifumi Yamaji, Daisuke Fujiwara
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90648
https://doi.org/10.1115/ICONE29-90648
View Paper titled, Evaluation of Effect of Depressurization Timing on the Thermal Load To Primary Containment Vessel During Severe Accident at BWR
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Topics: Accidents, Boiling water reactors, Containment vessels, Nuclear fission, Thermal loads
Proceedings Papers

Analysis of Reliability and Life of Fission Ionization Chamber of Nuclear Instrumentation System (NIS)

Yulin Zhou, Shunli Qiu, Mengtuan Ge, Guangzhi Sun, Wei Xiao, Haifeng Liu
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A030, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92683
https://doi.org/10.1115/ICONE29-92683
View Paper titled, Analysis of Reliability and Life of Fission Ionization Chamber of Nuclear Instrumentation System (NIS)
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Topics: Instrumentation, Ionization chambers, Nuclear fission, Reliability
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89461
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

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

Songyang Liu, Xiang Wang
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, V001T04A014, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65689
https://doi.org/10.1115/ICONE28-65689
View Paper titled, Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor
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Topics: Isotopes, Neutrons, Optimization, Physics, Small modular reactors, Temperature, Cycles, Design, Fuels, China
Proceedings Papers

Migration Characteristics of Sub-Source Items in Breach Occurrences

Xu Peng, Tian Ruifeng
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, V003T08A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64606
https://doi.org/10.1115/ICONE28-64606
View Paper titled, Migration Characteristics of Sub-Source Items in Breach Occurrences
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Topics: Accidents, Aerosols, Computational fluid dynamics, Computer software, Coolants, Drag (Fluid dynamics), Flow (Dynamics), Fluids, Gravity (Force), Hazards
Proceedings Papers

A Sodium-Cooled Thermal-Spectrum Fission Battery

Patrick J. McDaniel, Charles Forsberg
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, V001T04A015, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65765
https://doi.org/10.1115/ICONE28-65765
View Paper titled, A Sodium-Cooled Thermal-Spectrum Fission Battery
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Topics: Batteries, Nuclear fission, Sodium, Heat, Neutrons, Uranium, Carbon, Data centers, Design, Economics
Proceedings Papers

Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

Jin Feng Huang
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, V001T04A003, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63314
https://doi.org/10.1115/ICONE28-63314
View Paper titled, Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel
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Topics: Ceramics, Fuels, Pressurized water reactors, Cladding systems (Building), Cycles, Nuclear power stations, Silicon, Temperature, Thermal conductivity, Boron
Proceedings Papers

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Fengyang Quan, Wei Li, Zikun Zhao, Xiao Zeng, Yong Guo, Yidan Yuan
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A024, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64739
https://doi.org/10.1115/ICONE28-64739
View Paper titled, Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments
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Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux