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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
Article Type: Research-Article
Publisher: ASME
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
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
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
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
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
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
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
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

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

Junjie Rao, Xiaotong Shang, Kan Wang
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A010, July 22–26, 2018
Paper No: ICONE26-81694
https://doi.org/10.1115/ICONE26-81694
View Paper titled, Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark
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Topics: Pressure vessels, Computational methods, Neutron flux, Neutrons, Nuclear fission, Cavities, China, Neutron sources, Nuclear fuel cycle, Teams
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
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
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
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
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
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
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

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
https://doi.org/10.1115/ICONE26-81042
View Paper titled, Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”
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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
https://doi.org/10.1115/ICONE25-66519
View Paper titled, Newly Developed Coupling Scheme in RMC With Internal Thermal Feedback and OTF Doppler-Broadening Method
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Topics: Feedback, Nuclear reactors, Steady state, Fuels, Hydraulics, Manufacturing, Physics, Pressurized water reactors, Simulation, Simulation analysis
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
https://doi.org/10.1115/ICONE25-67082
View Paper titled, Public Acceptance of Spent Fuel Reprocessing Project
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Topics: Spent nuclear fuels, Nuclear power stations, Nuclear power, Uranium, Emissions, Gases, Nuclear engineering, Nuclear fuel cycle, Nuclear industry, Risk
Journal Articles

Quality Modeling of Printed Electronics in Aerosol Jet Printing Based on Microscopic Images

Hongyue Sun, Kan Wang, Yifu Li, Chuck Zhang, Ran Jin
Journal: Journal of Manufacturing Science and Engineering
Article Type: Research-Article
J. Manuf. Sci. Eng. July 2017, 139(7): 071012.
Paper No: MANU-16-1190
https://doi.org/10.1115/1.4035586
Published Online: April 10, 2017
View Article titled, Quality Modeling of Printed Electronics in Aerosol Jet Printing Based on Microscopic Images
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Topics: Aerosols, Electronics, Inks, Modeling, Printing, Silver, Errors
Proceedings Papers

Generalized Sensitivity Analysis With Continuous-Energy Monte Carlo Code RMC

Yishu Qiu, Manuele Aufiero, Kan Wang, Massimiliano Fratoni
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A033, June 26–30, 2016
Paper No: ICONE24-60473
https://doi.org/10.1115/ICONE24-60473
View Paper titled, Generalized Sensitivity Analysis With Continuous-Energy Monte Carlo Code RMC
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Topics: Collisions (Physics), Neutrons, Particulate matter, Perturbation theory, Sensitivity analysis, Tsunamis, Weight (Mass)
Proceedings Papers

A Three-Dimensional Flux Expansion Nodal Method for Hexagonal Geometry Application

Yun Cai, Xingjie Peng, Qing Li, Kan Wang, Wei Sun, Zhaohu Gong
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, V001T02A030, June 26–30, 2016
Paper No: ICONE24-61135
https://doi.org/10.1115/ICONE24-61135
View Paper titled, A Three-Dimensional Flux Expansion Nodal Method for Hexagonal Geometry Application
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Topics: Geometry, Currents, Diffusion (Physics), Eigenvalues, Flux (Metallurgy), Neutrons, Polynomials