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Proceedings Papers

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

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

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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

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

Paper No: ICONE29-92732

DOI: https://doi.org/10.1115/ICONE29-92732

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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

Paper No: ICONE29-90636

DOI: https://doi.org/10.1115/ICONE29-90636

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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

Paper No: ICONE29-93476

DOI: https://doi.org/10.1115/ICONE29-93476

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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

Paper No: ICONE29-92788

DOI: https://doi.org/10.1115/ICONE29-92788

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Topics: Failure, Fuel rods, Fuels, Nuclear fission, Pressurized water reactors, Cladding systems (Building), Rods, Irradiation (Radiation exposure)

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

Paper No: ICONE29-91240

DOI: https://doi.org/10.1115/ICONE29-91240

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Topics: Accidents, Bubbles, Computer simulation, Nuclear fission, Engineering simulation, Simulation, Water, Bifurcation, Design, Eutectic alloys

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

Paper No: ICONE29-92683

DOI: https://doi.org/10.1115/ICONE29-92683

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Topics: Instrumentation, Ionization chambers, Nuclear fission, Reliability

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

Paper No: ICONE29-90648

DOI: https://doi.org/10.1115/ICONE29-90648

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Topics: Accidents, Boiling water reactors, Containment vessels, Nuclear fission, Thermal loads

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

Paper No: ICONE29-91692

DOI: https://doi.org/10.1115/ICONE29-91692

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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

Paper No: ICONE29-89917

DOI: https://doi.org/10.1115/ICONE29-89917

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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission

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

Paper No: ICONE29-90448

DOI: https://doi.org/10.1115/ICONE29-90448

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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

Paper No: ICONE29-91659

DOI: https://doi.org/10.1115/ICONE29-91659

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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

Paper No: ICONE29-91275

DOI: https://doi.org/10.1115/ICONE29-91275

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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

Paper No: ICONE29-92642

DOI: https://doi.org/10.1115/ICONE29-92642

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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

Paper No: ICONE29-93353

DOI: https://doi.org/10.1115/ICONE29-93353

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Topics: Computational physics, Cross section (Physics), Design, Doppler effect, Feedback, Manufacturing, Neutrons, Nuclear design, Nuclear engineering, Nuclear fission

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

Paper No: ICONE28-65689

DOI: https://doi.org/10.1115/ICONE28-65689

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Topics: Isotopes, Neutrons, Optimization, Physics, Small modular reactors, Temperature, Cycles, Design, Fuels, China

Proceedings Papers

A Sodium-Cooled Thermal-Spectrum Fission Battery

Patrick J. McDaniel, Charles Forsberg

Paper No: ICONE28-65765

DOI: https://doi.org/10.1115/ICONE28-65765

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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

Paper No: ICONE28-63314

DOI: https://doi.org/10.1115/ICONE28-63314

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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

Paper No: ICONE28-64739

DOI: https://doi.org/10.1115/ICONE28-64739

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Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux

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

Paper No: ICONE28-64606

DOI: https://doi.org/10.1115/ICONE28-64606

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Topics: Accidents, Aerosols, Computational fluid dynamics, Computer software, Coolants, Drag (Fluid dynamics), Flow (Dynamics), Fluids, Gravity (Force), Hazards

2 3 4 5

NARROW

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

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

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

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

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

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

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

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

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

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

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

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

Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium

Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6

Validation of TULIP via ICSBEP Critical Benchmark

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

A Sodium-Cooled Thermal-Spectrum Fission Battery

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

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

Migration Characteristics of Sub-Source Items in Breach Occurrences

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