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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, V003T08A017, August 4–6, 2021

Paper No: ICONE28-65076

DOI: https://doi.org/10.1115/ICONE28-65076

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Topics: Ceramics, China, Computational fluid dynamics, Coolants, Design, Discrete element methods, Flow (Dynamics), Fusion reactors, Helium, Modeling

Proceedings Papers

Analysis of Friction Factor of Two-Phase Flow in Helically Coiled Tubes

Baihui Jiang, Zhiwei Zhou, Yu Ji

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A031, August 4–6, 2021

Paper No: ICONE28-64356

DOI: https://doi.org/10.1115/ICONE28-64356

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Topics: Friction, Two-phase flow

Proceedings Papers

Comparative Thermal Analyses Between Theoretical Mode and RELAP5 Code Simulation for OTSG of a Small PWR

Baihui Jiang, Zhiwei Zhou, Zhaoyang Xia, Qian Sun

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A018, August 4–5, 2020

Paper No: ICONE2020-16281

DOI: https://doi.org/10.1115/ICONE2020-16281

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Topics: Boilers, Circuits, Computer software, Construction, Design, Fluids, Heat, Heat transfer, Heat transfer coefficients, Light water reactors

Proceedings Papers

Power Rising and Descending Transient for the OTSG of a Small PWR

Baihui Jiang, Zhiwei Zhou, Zhaoyang Xia, Qian Sun

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A019, August 4–5, 2020

Paper No: ICONE2020-16294

DOI: https://doi.org/10.1115/ICONE2020-16294

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Topics: Flow instability, Pressurized water reactors, Transients (Dynamics), Boilers, Flow (Dynamics), Stability, Two-phase flow, Computer software, Fluids, Heat transfer

Proceedings Papers

Modification of RELAP/SCDAPSIM/MOD4.0 for Liquid Metal in Contact With Noncondensable Gas

Qian Sun, Tianji Peng, Zhiwei Zhou, Zhibin Chen, Shisheng Wang

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A022, July 22–26, 2018

Paper No: ICONE26-82030

DOI: https://doi.org/10.1115/ICONE26-82030

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Topics: Liquid metals, Safety, Modeling, Alloys, Fluids, Accidents, Coolants, Fast neutron reactors, Light water reactors, Lithium

Proceedings Papers

Investigation on Thermal-Hydraulic Parameters and Instability Under Two Different Heating Conditions Based on RELAP5 Code

Zhaoyang Xia, Zhiwei Zhou, Tianji Peng

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A048, July 22–26, 2018

Paper No: ICONE26-82268

DOI: https://doi.org/10.1115/ICONE26-82268

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Topics: Heating, Heat transfer, Critical heat flux, Heat, Superheating, Boilers, Density, Energy generation, Fluid dynamics, Oscillations

Journal Articles

Thermal-Hydraulic Model and Program Development for Helium-Cooled Accelerator-Driven System

Tianji Peng, Zhiwei Zhou

ASME J of Nuclear Rad Sci. April 2017, 3(2): 024502.

Paper No: NERS-16-1037

DOI: https://doi.org/10.1115/1.4035333

Published Online: March 1, 2017

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Topics: Heat, Heat transfer, Helium, Transients (Dynamics), Cooling systems, Mathematics, Fluids

Proceedings Papers

Transient Analysis on Helium Coolant Tube Break Accident of Dual-Functional Lithium Lead Test Blanket Module

Qian Sun, Tianji Peng, Zhiwei Zhou, Zhibin Chen, Jieqiong Jiang

Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A007, June 26–30, 2016

Paper No: ICONE24-60123

DOI: https://doi.org/10.1115/ICONE24-60123

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Topics: Accidents, Coolants, Helium, Lithium, Transient analysis, Pressure, Shock (Mechanics), China, Corners (Structural elements), Flow (Dynamics)

Proceedings Papers

Thermal-Hydraulic Design and Transient Analysis of Helium-Cooled Solid Target for ADS

Tianji Peng, Zhiwei Zhou, Long Gu

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A009, July 7–11, 2014

Paper No: ICONE22-30082

DOI: https://doi.org/10.1115/ICONE22-30082

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Topics: Design, Helium, Transient analysis, Honeycomb structures, Spallation (Nuclear physics), Cooling systems, Transients (Dynamics), Chain, Computational fluid dynamics, Flow (Dynamics)

Proceedings Papers

Preliminary Severe Accident Analysis of Fusion-Fission Hybrid Reactor Using the MELCOR Code

Zhang Dabin, Zhiwei Zhou, Heng Xie, Tang Yang

Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A022, July 7–11, 2014

Paper No: ICONE22-30644

DOI: https://doi.org/10.1115/ICONE22-30644

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Topics: Accidents, Nuclear fission, Vessels, Cooling, Heat, Safety, Water, Cooling systems, Energy generation, Fuels

Proceedings Papers

HTR-PM Simulation Analysis of Accident Conditions Based on vPower Platform

Tang Yang, Yangping Zhou, Zhiwei Zhou, Zhang Dabin

Paper No: ICONE22-30726

DOI: https://doi.org/10.1115/ICONE22-30726

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Topics: Accidents, Simulation analysis, Boilers, Cycles, Design, Energy generation, Flow (Dynamics), Helium, Safety, Simulation

Proceedings Papers

Assessment Study of RELAP5/SCDAP Capability to Reproduce Liquid Metal Fluid Thermal Hydraulic Behaviour

F. Fiori, Zhiwei Zhou

Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A010, July 7–11, 2014

Paper No: ICONE22-30612

DOI: https://doi.org/10.1115/ICONE22-30612

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Topics: Fluids, Liquid metals, Heat transfer, Coolants, Databases, Design, Flow (Dynamics), Heat exchangers, Safety, Transients (Dynamics)

Proceedings Papers

Improving Thermal-Hydraulic Calculation Modules of THERMIX Code Based on LU Decomposition

Yang Tang, Yangping Zhou, Zhiwei Zhou

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A104, July 29–August 2, 2013

Paper No: ICONE21-16575

DOI: https://doi.org/10.1115/ICONE21-16575

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Topics: Accidents, Accuracy and precision, Computer software, Flow (Dynamics), Gas flow, Safety, Storage, Thermal conductivity, Very high temperature reactors

Proceedings Papers

Thermal-Hydraulic Analysis of Concept Design of Spallation Target in Chinese Accelerator Driven Subcritical System

Zhiwei Zhou, Yaoli Zhang, Sicong Xiao, Yongwei Yang

Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 721-726, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-55134

DOI: https://doi.org/10.1115/ICONE20-POWER2012-55134

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Topics: Design, Spallation (Nuclear physics), Computational fluid dynamics, Coolants, Heat, Neutron sources, Shapes, Temperature distribution, Transmutation (Nuclear physics)

Proceedings Papers

The Sensitivity Analysis of Passive Containment Cooling System During Design Basis Accidents

Zhiwei Zhou, Yaoli Zhang, Yanning Yang

Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 727-732, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-55136

DOI: https://doi.org/10.1115/ICONE20-POWER2012-55136

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Topics: Accidents, Containment, Cooling systems, Design, Sensitivity analysis, Flow (Dynamics), Pressure, Temperature, Vacuum, Cooling

Proceedings Papers

IVR Model Study for Passive PWR

Hong Xu, Peng Zhang, Zhiwei Zhou

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 393-399, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54613

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54613

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Topics: Accidents, Pressurized water reactors, Vessels, Safety, Cooling, Design, Reactor vessels, Construction, Containment, Economics

Proceedings Papers

Compact Engineering Simulator for HTR-PM by Embedding THERMIX Code in vPower Simulation Platform

Qiang Gao, Yangping Zhou, Zhiwei Zhou, Zhe Sui, Yuanle Ma, Fu Li

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 543-549, May 17–21, 2010

Paper No: ICONE18-29437

DOI: https://doi.org/10.1115/ICONE18-29437

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Topics: Simulation, Design, Boilers, Cycles, Energy generation, Machinery, Safety, Simulation results, Steam, Very high temperature reactors

Proceedings Papers

Study on Neutronics and Fuel Cycle of Fusion-Fission Hybrid Reactor

Hong Xu, Yongwei Yang, Zhiwei Zhou

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 641-644, May 17–21, 2010

Paper No: ICONE18-30048

DOI: https://doi.org/10.1115/ICONE18-30048

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Topics: Nuclear fission, Nuclear fuel cycle, Fuels, Coolants, Alloys, Conceptual design, Plasmas (Ionized gases), Water, Zirconium

Journal citation

NARROW

Study on Aerosol Growth and Deposition Properties Affected by Steam Condensation

Prediction of Sound Radiation From Vibrating Structures in Motion: Application to Vehicle Pass-By Noises

Tritium Transport Modeling and Analysis for HCCB Blanket of CFETR

Analysis of Friction Factor of Two-Phase Flow in Helically Coiled Tubes

Comparative Thermal Analyses Between Theoretical Mode and RELAP5 Code Simulation for OTSG of a Small PWR

Power Rising and Descending Transient for the OTSG of a Small PWR

Modification of RELAP/SCDAPSIM/MOD4.0 for Liquid Metal in Contact With Noncondensable Gas

Investigation on Thermal-Hydraulic Parameters and Instability Under Two Different Heating Conditions Based on RELAP5 Code

Thermal-Hydraulic Model and Program Development for Helium-Cooled Accelerator-Driven System

Transient Analysis on Helium Coolant Tube Break Accident of Dual-Functional Lithium Lead Test Blanket Module

Thermal-Hydraulic Design and Transient Analysis of Helium-Cooled Solid Target for ADS

Preliminary Severe Accident Analysis of Fusion-Fission Hybrid Reactor Using the MELCOR Code

HTR-PM Simulation Analysis of Accident Conditions Based on vPower Platform

Assessment Study of RELAP5/SCDAP Capability to Reproduce Liquid Metal Fluid Thermal Hydraulic Behaviour

Improving Thermal-Hydraulic Calculation Modules of THERMIX Code Based on LU Decomposition

Thermal-Hydraulic Analysis of Concept Design of Spallation Target in Chinese Accelerator Driven Subcritical System

The Sensitivity Analysis of Passive Containment Cooling System During Design Basis Accidents

IVR Model Study for Passive PWR

Compact Engineering Simulator for HTR-PM by Embedding THERMIX Code in vPower Simulation Platform

Study on Neutronics and Fuel Cycle of Fusion-Fission Hybrid Reactor

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