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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

DOI: https://doi.org/10.1115/ICONE29-93103

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Topics: Computer-aided design, Engineering simulation, Geometry, Nuclear reactors, Particulate matter, Physics, Simulation, Transport processes, Weight (Mass)

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

DOI: https://doi.org/10.1115/ICONE29-93476

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Topics: Algorithms, Cycles, Nuclear fission

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

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

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

DOI: https://doi.org/10.1115/ICONE2020-16066

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Topics: Interpolation, Neutron diffraction

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

DOI: https://doi.org/10.1115/ICONE26-82397

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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

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

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

DOI: https://doi.org/10.1115/ICONE26-81694

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Topics: Pressure vessels, Computational methods, Neutron flux, Neutrons, Nuclear fission, Cavities, China, Neutron sources, Nuclear fuel cycle, Teams

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

DOI: https://doi.org/10.1115/ICONE26-81140

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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

DOI: https://doi.org/10.1115/ICONE26-81982

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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

DOI: https://doi.org/10.1115/ICONE26-82185

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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

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

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

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

J. Manuf. Sci. Eng. July 2017, 139(7): 071012.

Paper No: MANU-16-1190

DOI: https://doi.org/10.1115/1.4035586

Published Online: April 10, 2017

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Topics: Aerosols, Electronics, Inks, Modeling, Printing, Silver, Errors

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

DOI: https://doi.org/10.1115/ICONE24-61135

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Topics: Geometry, Currents, Diffusion (Physics), Eigenvalues, Flux (Metallurgy), Neutrons, Polynomials

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

DOI: https://doi.org/10.1115/ICONE24-60473

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Topics: Collisions (Physics), Neutrons, Particulate matter, Perturbation theory, Sensitivity analysis, Tsunamis, Weight (Mass)

Journal citation

NARROW

Manuscript

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

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

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

Research on the Correlations of Fission Source Distribution in the Monte Carlo Algorithm Using Mathematical Tools

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

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

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

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”

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

Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC

Enhancement of Stochastic Sampling Capability in RMC Code

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

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

Public Acceptance of Spent Fuel Reprocessing Project

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

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

Generalized Sensitivity Analysis With Continuous-Energy Monte Carlo Code RMC

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