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Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A002, August 8–12, 2022

Paper No: ICONE29-88883

DOI: https://doi.org/10.1115/ICONE29-88883

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Topics: Damage, Fuels, Nuclides, Pressurized water reactors, Very high temperature reactors

Proceedings Papers

Preliminary Simulations on the Atmospheric Dispersion of Radioactive Substance for the Two Sites in Tunisia

Elyes Ghannouchi, Yu Wang, Jianzhu Cao, Feng Xie, Liguo Zhang, Jiejuan Tong, Rentai Yao, Khaled Debbabi

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, V003T12A009, August 4–6, 2021

Paper No: ICONE28-63536

DOI: https://doi.org/10.1115/ICONE28-63536

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Topics: Engineering simulation, Radioactive substances, Simulation

Proceedings Papers

Transport Behavior of Silver in High-Temperature Gas-Cooled Reactors

Yu Wang, Jianzhu Cao, Feng Xie, Xiaobao Yang, Peng Li, Jie Ma, Xianbao Duan

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A013, August 4–6, 2021

Paper No: ICONE28-63484

DOI: https://doi.org/10.1115/ICONE28-63484

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Topics: Silver, Very high temperature reactors

Proceedings Papers

Neutronic/Thermal-Hydraulic Coupling Analysis of Xi'an Pulsed Reactor Based on RMC and COBRA-TF

Ruihan Li, Jianzhu Cao, Lipeng Wang, Xinyi Zhang, Xiaoyu Guo, Jingang Liang

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A059, August 4–6, 2021

Paper No: ICONE28-64623

DOI: https://doi.org/10.1115/ICONE28-64623

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Topics: Fuel rods, Monte Carlo methods, Neutrons, Physics, Simulation, Steady state, Temperature

Proceedings Papers

Design of the Important Area Airborne Radioactivity Monitoring System and Calculation of the Alarm Threshold of HTR-PM

Wenqian Li, Chuan Li, Jianzhu Cao, Feng Xie

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A007, July 22–26, 2018

Paper No: ICONE26-81232

DOI: https://doi.org/10.1115/ICONE26-81232

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Topics: Design, Monitoring systems, Radioactivity, Pressurized water reactors, Coolants, Radiation measurement, Emergencies, Feedback, Gases, Helium

Proceedings Papers

Design of the Sampling Measurement and Radiochemistry Lab in the Nuclear Island of HTR-PM

Mengqi Lou, Wenqian Li, Feng Xie, Jianzhu Cao, Liqiang Wei, Jiejuan Tong, Jiaji Kong

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A020, July 22–26, 2018

Paper No: ICONE26-81701

DOI: https://doi.org/10.1115/ICONE26-81701

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Topics: Design, Instrumentation, Regulations, Coolants, Dust, Germanium, Helium, Nuclear power stations, Radiation measurement, Radiation measuring instruments

Proceedings Papers

Generation and Distribution of Tritium in HTGRs and Review on the Tritiated Water Treatment Technologies

Fuming Jia, Feng Xie, Hong Li, Jianzhu Cao

Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A006, July 2–6, 2017

Paper No: ICONE25-66417

DOI: https://doi.org/10.1115/ICONE25-66417

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Topics: Very high temperature reactors, Water treatment, Nuclear power stations, Water, Graphite, Lithium, Boron, Bricks, Carbon, Coolants

Proceedings Papers

Design of the Area Radiation Monitoring System in Nuclear Island of HTR-PM

Feng Xie, Jiaji Kong, Hongqi Liu, Jianzhu Cao

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A045, July 2–6, 2017

Paper No: ICONE25-66415

DOI: https://doi.org/10.1115/ICONE25-66415

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Topics: Design, Radiation measurement, Radiation (Physics), Pressurized water reactors, Very high temperature reactors, China, Instrumentation, Irradiation (Radiation exposure), Nuclear power stations, Power stations

Proceedings Papers

Methodology to Construct Burnup Profile of Fuel Pebbles in PBR

Yushi Tang, Liguo Zhang, Qiuju Guo, Jianzhu Cao, Jiejuan Tong

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A029, July 2–6, 2017

Paper No: ICONE25-66795

DOI: https://doi.org/10.1115/ICONE25-66795

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Topics: Fuels, Discrete element methods, Flow (Dynamics), Economics , Safety, Cycles, Gas cooled reactors, Irradiation (Radiation exposure), Kinematics, Simulation

Proceedings Papers

Design of the Process and Effluent Radiation Monitoring System of HTR-PM

Feng Xie, Wenqian Li, Zhihui Li, Jianzhu Cao, Hong Li, Jiejuan Tong, Haitao Wang

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, V001T03A031, June 26–30, 2016

Paper No: ICONE24-61008

DOI: https://doi.org/10.1115/ICONE24-61008

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Topics: Design, Radiation measurement, Pressurized water reactors, Very high temperature reactors, Carbon, Coolants, Dust, Fuels, Helium, Nuclear fission

Proceedings Papers

A Proposed Model to Describe the Relationship Between Online Burnup Assay and Economy and Safety of Pebble Bed Reactor

Yushi Tang, Liguo Zhang, Quiju Guo, Jianzhu Cao, Jiejuan Tong

Paper No: ICONE24-60175

DOI: https://doi.org/10.1115/ICONE24-60175

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Topics: Economics , Safety, Fuels, Gas cooled reactors, Irradiation (Radiation exposure), Probability, Reliability

Proceedings Papers

Optimization of the Radiation Shielding Program QAD

Wenyi Wang, Liguo Zhang, Jianzhu Cao, Feng Xie

Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T11A013, June 26–30, 2016

Paper No: ICONE24-60938

DOI: https://doi.org/10.1115/ICONE24-60938

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Topics: Optimization, Radiation (Physics), Algorithms, Cylinders, Design, Geometry, Nuclear power stations

Proceedings Papers

A Reform in the Helium Purification System of the HTR-10: γ Dose Rate Measurement and Suggestions for Decommissioning

Feng Xie, Hong Li, Jianzhu Cao, Suyuan Yu, Liguo Zhang, Wenqian Li, Sheng Fang

Proc. ASME. ICEM2013, Volume 2: Facility Decontamination and Decommissioning; Environmental Remediation; Environmental Management/Public Involvement/Crosscutting Issues/Global Partnering, V002T03A019, September 8–12, 2013

Paper No: ICEM2013-96095

DOI: https://doi.org/10.1115/ICEM2013-96095

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Topics: Helium, Nuclear decommissioning, Dust, Filters, High temperature, China, Decontamination, Nuclides, Pipes, Radiation (Physics)

Proceedings Papers

γ Dose Rate Estimation and Operation Management Suggestions for Decommissioning the Reactor Pressure Vessel of HTR-PM

Sheng Fang, Hong Li, Jianzhu Cao, Wenqian Li, Feng Xie, Jiejuan Tong

Paper No: ICEM2013-96018

DOI: https://doi.org/10.1115/ICEM2013-96018

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Topics: Nuclear decommissioning, Reactor vessels, China, Cooling, Design, High temperature, Radiation (Physics)

Proceedings Papers

Decommissioning for the Containment Vessel of HTR-PM: Monte Carlo Simulation and Long-Time Predictions

Wenqian Li, Hong Li, Jianzhu Cao, Ming Li, Feng Xie, Sheng Fang

Paper No: ICEM2013-96078

DOI: https://doi.org/10.1115/ICEM2013-96078

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Topics: Containment vessels, Nuclear decommissioning, Simulation, China, Concretes, Construction, Design, Engineering standards, High temperature, Particulate matter

Proceedings Papers

Analysis of Radioactive Source Term for Modular HTGR During Normal Operation

Jianzhu Cao, Tao Liu, Yuanyu Wu, Hong Li, Yuanzhong Liu

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 297-302, May 17–21, 2010

Paper No: ICONE18-30075

DOI: https://doi.org/10.1115/ICONE18-30075

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Topics: Very high temperature reactors, China, Circuits, Nuclear fission, Design, Gas cooled reactors, High temperature, Nuclides

Proceedings Papers

Analysis of Tritium Production and Distribution in HTR-PM

Yuanyu Wu, Jianzhu Cao

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 703-707, May 17–21, 2010

Paper No: ICONE18-30147

DOI: https://doi.org/10.1115/ICONE18-30147

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Topics: Alloys, Design, Differential equations, Fuels, Heat exchangers, Neutrons, Nuclear fission, Nuclides, Oxidation, Radiation (Physics)

Journal citation

NARROW

Research on Wastewater Source Term in High-Temperature Gas-Cooled Reactor and the Environmental Impact at Inland Sites

3-D Radiation Field Reconstruction for a Facility With Multiple Radioactive Sources

Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs

Preliminary Simulations on the Atmospheric Dispersion of Radioactive Substance for the Two Sites in Tunisia

Transport Behavior of Silver in High-Temperature Gas-Cooled Reactors

Neutronic/Thermal-Hydraulic Coupling Analysis of Xi'an Pulsed Reactor Based on RMC and COBRA-TF

Design of the Important Area Airborne Radioactivity Monitoring System and Calculation of the Alarm Threshold of HTR-PM

Design of the Sampling Measurement and Radiochemistry Lab in the Nuclear Island of HTR-PM

Generation and Distribution of Tritium in HTGRs and Review on the Tritiated Water Treatment Technologies

Design of the Area Radiation Monitoring System in Nuclear Island of HTR-PM

Methodology to Construct Burnup Profile of Fuel Pebbles in PBR

Design of the Process and Effluent Radiation Monitoring System of HTR-PM

A Proposed Model to Describe the Relationship Between Online Burnup Assay and Economy and Safety of Pebble Bed Reactor

Optimization of the Radiation Shielding Program QAD

A Reform in the Helium Purification System of the HTR-10: γ Dose Rate Measurement and Suggestions for Decommissioning

γ Dose Rate Estimation and Operation Management Suggestions for Decommissioning the Reactor Pressure Vessel of HTR-PM

Decommissioning for the Containment Vessel of HTR-PM: Monte Carlo Simulation and Long-Time Predictions

Analysis of Radioactive Source Term for Modular HTGR During Normal Operation

Analysis of Tritium Production and Distribution in HTR-PM

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