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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, V001T02A020, August 4–6, 2021

Paper No: ICONE28-64532

DOI: https://doi.org/10.1115/ICONE28-64532

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Topics: Simulation, Teaching, Very high temperature reactors, Accidents, Nuclear engineering, Nuclear industry, Students, Boilers, Control systems, Design

Proceedings Papers

A Sodium-Cooled Fast Reactor Simulation System and its Application In Teaching Research Based on VPOWER Platform

Chengzhi Ji, Biheng Xie, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang

Paper No: ICONE28-64364

DOI: https://doi.org/10.1115/ICONE28-64364

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Topics: Simulation, Sodium fast reactors, Teaching

Proceedings Papers

Calculation of Probability of Survival (POS) in Dynamic Systems Based on RMC Code

Conglong Jia, Guanlin Shi, Zhiyuan Feng, Xiaoyu Guo, Kan Wang, Shanfang Huang, Jingang Liang

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A021, August 4–6, 2021

Paper No: ICONE28-64077

DOI: https://doi.org/10.1115/ICONE28-64077

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Topics: Dynamic systems, Probability, Neutrons, Chain, Interpolation, Neutron sources, Particulate matter, Simulation

Proceedings Papers

Reforms and Innovations in a Nuclear Engineering Course: Nuclear Power Plant Systems and Equipment

Shanfang Huang, Jiageng Wang, Yisheng Hao, Guodong Liu, Minyun Liu, Yugao Ma

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T07A001, August 4–5, 2020

Paper No: ICONE2020-16033

DOI: https://doi.org/10.1115/ICONE2020-16033

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Topics: Innovation, Nuclear engineering, Nuclear power stations, Safety, Teaching

Proceedings Papers

Nuclear Data Sensitivity and Uncertainty Analysis for Generalized Response With RMC Code

Guanlin Shi, Conglong Jia, Shanfang Huang, Kaiwen Li, Lei Zheng

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A003, August 4–5, 2020

Paper No: ICONE2020-16062

DOI: https://doi.org/10.1115/ICONE2020-16062

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Topics: Uncertainty analysis

Proceedings Papers

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs

Yugao Ma, Minyun Liu, Wenbin Han, Biheng Xie, Xiaoming Chai, Shanfang Huang, Hongxing Yu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A006, August 4–5, 2020

Paper No: ICONE2020-16100

DOI: https://doi.org/10.1115/ICONE2020-16100

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Topics: Heat pipes, Feedback, Geometry, Heat transfer, Construction, Design, Finite element analysis, Finite element methods, High temperature, Light water reactors

Proceedings Papers

A Universal Adjoint-Weighted Algorithm for Geometric Sensitivity Analysis of K-Eigenvalue Based on Continuous-Energy Monte Carlo Method

Hao Li, Ganglin Yu, Shanfang Huang, Kan Wang

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A093, July 22–26, 2018

Paper No: ICONE26-82494

DOI: https://doi.org/10.1115/ICONE26-82494

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Topics: Algorithms, Eigenvalues, Geometry, Monte Carlo methods, Neutrons, Rotation, Sensitivity analysis

Proceedings Papers

Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”

Shanfang Huang, Yaopeng Gong, Chao Li, Ruilong Liu, Jiageng Wang, Kan Wang

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T12A002, July 22–26, 2018

Paper No: ICONE26-81042

DOI: https://doi.org/10.1115/ICONE26-81042

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Topics: Computer simulation, Education, Nuclear engineering, Nuclear reactors, Thermal analysis, Nuclear power, China, Computer software, Computers, Experimental design

Proceedings Papers

Newly Developed Coupling Scheme in RMC With Internal Thermal Feedback and OTF Doppler-Broadening Method

Ouwen Yexin, Shanfang Huang, Kan Wang

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A014, July 2–6, 2017

Paper No: ICONE25-66519

DOI: https://doi.org/10.1115/ICONE25-66519

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Topics: Feedback, Nuclear reactors, Steady state, Fuels, Hydraulics, Manufacturing, Physics, Pressurized water reactors, Simulation, Simulation analysis

Proceedings Papers

The Numerical Simulation Research of Gas Entrainment Based on Three-Dimensional Model

Yilin Zhang, Shanfang Huang

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A025, July 2–6, 2017

Paper No: ICONE25-66725

DOI: https://doi.org/10.1115/ICONE25-66725

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Topics: Computer simulation, Three-dimensional models, Flow (Dynamics), Porosity, Simulation results, Coolants, External pressure, Fluid density, Fluids, Fracture (Materials)

Proceedings Papers

Public Acceptance of Spent Fuel Reprocessing Project

Zijian Wang, Shanfang Huang, Xiaoyu Guo, Kan Wang

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T12A008, July 2–6, 2017

Paper No: ICONE25-67082

DOI: https://doi.org/10.1115/ICONE25-67082

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Topics: Spent nuclear fuels, Nuclear power stations, Nuclear power, Uranium, Emissions, Gases, Nuclear engineering, Nuclear fuel cycle, Nuclear industry, Risk

Proceedings Papers

Evaluation of Passive Circulation Flow Characteristics and CHF Under In-Vessel Retention

Qiang Hu, Xiao Yan, Shanfang Huang, Yanping Huang, JunChong Yu

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A032, June 26–30, 2016

Paper No: ICONE24-60507

DOI: https://doi.org/10.1115/ICONE24-60507

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Topics: Critical heat flux, Flow (Dynamics), Vessels, Heating, Reactor vessels, Accidents, Clearances (Engineering), Cooling, Energy conservation, Floods

Proceedings Papers

Thermal-Hydraulic Analysis for Experimental Device of Supercritical Water Reactor-Fuel Qualification Test

Liang Liu, Tao Zhou, Yu Li, Wanxu Cheng, Juan Chen, Shanfang Huang, Yanping Huang

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A025, July 7–11, 2014

Paper No: ICONE22-30176

DOI: https://doi.org/10.1115/ICONE22-30176

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Topics: China, Coolants, Design, Flow (Dynamics), Nuclear fuels, Pressure, Safety, Stability, Supercritical water reactors, Temperature

Proceedings Papers

Analytical Prediction of Turbulent Friction Factor in Circular Pipe Under Supercritical Conditions

Jinguang Zang, Xiao Yan, Shanfang Huang, Zejun Xiao, Yanping Huang

Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 741-750, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-55159

DOI: https://doi.org/10.1115/ICONE20-POWER2012-55159

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Topics: Flow (Dynamics), Friction, Pipes, Turbulence, Density, Viscosity, Algebra, Fluids, Theoretical analysis

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Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor with SiC Matrix and TRISO Particle Fuel

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC

Neutronic and Thermal-Hydraulic Analyses for an Additive Manufacturing Reactor Core With SiC Matrix and TRISO Particle Fuel

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on RMC

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

A Sodium-Cooled Fast Reactor Simulation System and its Application In Teaching Research Based on VPOWER Platform

Calculation of Probability of Survival (POS) in Dynamic Systems Based on RMC Code

Reforms and Innovations in a Nuclear Engineering Course: Nuclear Power Plant Systems and Equipment

Nuclear Data Sensitivity and Uncertainty Analysis for Generalized Response With RMC Code

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe Cooled Reactor Designs

A Universal Adjoint-Weighted Algorithm for Geometric Sensitivity Analysis of K-Eigenvalue Based on Continuous-Energy Monte Carlo Method

Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”

Newly Developed Coupling Scheme in RMC With Internal Thermal Feedback and OTF Doppler-Broadening Method

The Numerical Simulation Research of Gas Entrainment Based on Three-Dimensional Model

Public Acceptance of Spent Fuel Reprocessing Project

Evaluation of Passive Circulation Flow Characteristics and CHF Under In-Vessel Retention

Thermal-Hydraulic Analysis for Experimental Device of Supercritical Water Reactor-Fuel Qualification Test

Analytical Prediction of Turbulent Friction Factor in Circular Pipe Under Supercritical Conditions

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