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Journal Articles

GPU-Accelerated Full-Wheel Large-Eddy Simulations of a Transonic Fan Stage

Kan Wang, Sanjeeb Bose, Christopher Ivey
Journal: Journal of Turbomachinery
Publisher: ASME
Article Type: Research Papers
J. Turbomach. August 2025, 147(8): 081003.
Paper No: TURBO-24-1191
https://doi.org/10.1115/1.4067176
Published Online: January 13, 2025
View Article titled, GPU-Accelerated Full-Wheel Large-Eddy Simulations of a Transonic Fan Stage
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Topics: Blades, Engineering simulation, Graphics processing units, Large eddy simulation, Rotors, Simulation, Wheels, Pressure, Flow (Dynamics), Clearances (Engineering)
Proceedings Papers

Research on the ODR-VS Method Applicable to Various Geometric Models

Zhiyuan Feng, Jingang Liang, Wenli Guo, Kan Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A032, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134943
https://doi.org/10.1115/ICONE31-134943
View Paper titled, Research on the ODR-VS Method Applicable to Various Geometric Models
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Topics: Ceramics, Cylinders, Discrete element methods, Ductility, Fuels, Geometric modeling, Metals, Modeling, Neutrons, Nuclear fuels
Proceedings Papers

Weight Window Generation Based on Pre-Calculated Response Matrix

Yingzhe Hu, Pengfei Shen, Shihang Jiang, Shanfang Huang, Kan Wang, Zeguang Li, Zhaoyuan Liu
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A023, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134556
https://doi.org/10.1115/ICONE31-134556
View Paper titled, Weight Window Generation Based on Pre-Calculated Response Matrix
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Topics: Weight (Mass), Generators, Simulation
Proceedings Papers

Multi-Mesh Approach for Geometry-Independent Neutronic/Thermal-Hydraulics Coupling Analyses Using RMC and Ansys Fluent

Xingyu Zhao, Guodong Liu, Shanfang Huang, Qiaoyan Chen, Hao Luo, Ying He, Junren Hou, Kan Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133607
https://doi.org/10.1115/ICONE31-133607
View Paper titled, Multi-Mesh Approach for Geometry-Independent Neutronic/Thermal-Hydraulics Coupling Analyses Using RMC and Ansys Fluent
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Topics: Computational fluid dynamics, Geometry, Thermal hydraulics
Proceedings Papers

AWCC Simulations Based on Monte Carlo Code RMC

Yuanhao Gou, Zhaoyuan Liu, Conglong Jia, Dacai Zhang, Hao Luo, Kan Wang
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132066
https://doi.org/10.1115/ICONE31-132066
View Paper titled, AWCC Simulations Based on Monte Carlo Code RMC
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Topics: Design, Emissions, Engineering simulation, Gates (Closures), Instrumentation, Neutrons, Nuclear fission, Simulation, Uranium
Proceedings Papers

An Improved Multiphase Lattice Boltzmann Method Scheme for Large Density Ratio Simulation in Heat Pipe

Lie Quan, Yugao Ma, Xiao Liu, Shanfang Huang, Kan Wang
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A052, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135207
https://doi.org/10.1115/ICONE31-135207
View Paper titled, An Improved Multiphase Lattice Boltzmann Method Scheme for Large Density Ratio Simulation in Heat Pipe
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Topics: Density, Heat pipes, Lattice Boltzmann methods, Multiphase flow, Simulation
Proceedings Papers

GPU-Accelerated Full-Wheel Large-Eddy Simulations of a Transonic Fan Stage

Kan Wang, Sanjeeb Bose, Christopher Ivey
Proc. ASME. GT2024, Volume 12C: Turbomachinery — Design Methods and CFD Modeling for Turbomachinery; Ducts, Noise, and Component Interactions, V12CT32A042, June 24–28, 2024
Publisher: American Society of Mechanical Engineers
Paper No: GT2024-128238
https://doi.org/10.1115/GT2024-128238
View Paper titled, GPU-Accelerated Full-Wheel Large-Eddy Simulations of a Transonic Fan Stage
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Topics: Graphics processing units, Large eddy simulation, Wheels
Journal Articles

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

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041103.
Paper No: NERS-22-1137
https://doi.org/10.1115/1.4056772
Published Online: May 31, 2023
View Article titled, Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code
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Topics: Coolants, Design, Diluents, Fuels, Leakage, Neutrons, Supercritical carbon dioxide, Nuclear fission, Nuclides, Feedback
Proceedings Papers

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

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A073, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92054
https://doi.org/10.1115/ICONE29-92054
View Paper titled, Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on RMC
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Topics: Coolants, Design, Supercritical carbon dioxide, Yttrium
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

Implementation and Verification of the DAGMC Module in Monte Carlo Code RMC

Pengfei Shen, Jingang Liang, Shichang Liu, Kan Wang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A075, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93103
https://doi.org/10.1115/ICONE29-93103
View Paper titled, Implementation and Verification of the DAGMC Module in Monte Carlo Code RMC
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Topics: Computer-aided design, Engineering simulation, Geometry, Nuclear reactors, Particulate matter, Physics, Simulation, Transport processes, Weight (Mass)
Proceedings Papers

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

Biheng Xie, Chengzhi Ji, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64532
https://doi.org/10.1115/ICONE28-64532
View Paper titled, A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform
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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
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, V001T01A005, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64364
https://doi.org/10.1115/ICONE28-64364
View Paper titled, A Sodium-Cooled Fast Reactor Simulation System and its Application In Teaching Research Based on VPOWER Platform
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64077
https://doi.org/10.1115/ICONE28-64077
View Paper titled, Calculation of Probability of Survival (POS) in Dynamic Systems Based on RMC Code
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Topics: Dynamic systems, Probability, Neutrons, Chain, Interpolation, Neutron sources, Particulate matter, Simulation
Proceedings Papers

On-the-Fly Treatment of Discrete Representation Thermal Neutron Scattering Data in RMC Code

Lei Zheng, Kaiwen Li, Kan Wang
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A001, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16066
https://doi.org/10.1115/ICONE2020-16066
View Paper titled, On-the-Fly Treatment of Discrete Representation Thermal Neutron Scattering Data in RMC Code
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Topics: Interpolation, Neutron diffraction
Proceedings Papers

Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC

Wanlin Li, Kan Wang, Ganglin Yu, Yaodong Li
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A005, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81140
https://doi.org/10.1115/ICONE26-81140
View Paper titled, Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC
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Topics: Approximation, Computational methods, Cross section (Physics), Density, Design, Errors, Geometry, Manufacturing, Modeling, Neutron flux
Proceedings Papers

Enhancement of Stochastic Sampling Capability in RMC Code

Guanlin Shi, Yishu Qiu, Kan Wang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A035, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81982
https://doi.org/10.1115/ICONE26-81982
View Paper titled, Enhancement of Stochastic Sampling Capability in RMC Code
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Topics: Algorithms, Nuclear fission, Safety, Sampling methods, Uncertainty, Uncertainty analysis, Uncertainty quantification
Proceedings Papers

One Step Method for Multigroup Adjoint Neutron Flux Through Continuous Energy Monte Carlo Calculation

Xiaotong Shang, Guanlin Shi, Kan Wang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A043, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82185
https://doi.org/10.1115/ICONE26-82185
View Paper titled, One Step Method for Multigroup Adjoint Neutron Flux Through Continuous Energy Monte Carlo Calculation
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Topics: Neutron flux, Neutrons, Nuclear fission, Transients (Dynamics), Cross section (Physics), Event history analysis, Monte Carlo methods, Nuclear reactor kinetics, Probability, Transient analysis
Proceedings Papers

Internal Coupling Between Neutronics and Thermal-Hydraulics With RMC/CTF and Validation Using VERA Benchmarks

Kaiwen Li, Shichang Liu, Juanjuan Guo, Kan Wang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A054, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82397
https://doi.org/10.1115/ICONE26-82397
View Paper titled, Internal Coupling Between Neutronics and Thermal-Hydraulics With RMC/CTF and Validation Using VERA Benchmarks
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Topics: Manufacturing, Thermal hydraulics, Virtual reality
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82494
https://doi.org/10.1115/ICONE26-82494
View Paper titled, A Universal Adjoint-Weighted Algorithm for Geometric Sensitivity Analysis of K-Eigenvalue Based on Continuous-Energy Monte Carlo Method
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Topics: Algorithms, Eigenvalues, Geometry, Monte Carlo methods, Neutrons, Rotation, Sensitivity analysis