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Proceedings Papers

Digital Twin-Driven Development of Online Monitoring and Data Management Systems in TMSR-SF0

Wen-Qian Liu, Li-Feng Han, Li Huang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A026, August 8–12, 2022
Paper No: ICONE29-92770
https://doi.org/10.1115/ICONE29-92770
View Paper titled, Digital Twin-Driven Development of Online Monitoring and Data Management Systems in TMSR-SF0
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Topics: Data collection, Data storage systems, Databases, Design, Digital twin, Engines, Fuels, Industrial controls, Modeling, Molten salt reactors
Proceedings Papers

The Core Design Modifications for Stirling Thermal-Electric Integrated Micro Reactor

Xia Yan, Xuedong Ou, Mingqiang Lin, Jian Mou, Shaolei Sun, Chunyun Chi, Chunqing Zhao, Qin Zhou
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A045, August 8–12, 2022
Paper No: ICONE29-93465
https://doi.org/10.1115/ICONE29-93465
View Paper titled, The Core Design Modifications for Stirling Thermal-Electric Integrated Micro Reactor
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Topics: Design, Fuels, Compression, Coolants, Flow (Dynamics), Generators, Gravity (Force), Heat, Heat transfer, Nuclear design
Proceedings Papers

Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes

Yuan Yuan, Guoming Liu, Xiaodong Huo
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A006, August 8–12, 2022
Paper No: ICONE29-92520
https://doi.org/10.1115/ICONE29-92520
View Paper titled, Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes
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Topics: Chemical kinetics, Cross section (Physics), Fast neutron reactors, Geometry, Manufacturing, Modeling, Physics, Relaxation (Physics), Very high temperature reactors
Proceedings Papers

Verification and Validation of JMCT Monte Carlo Code in CPR1000

Yaoxin Ye, Jun Zhao, Pengfei Bao
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A009, August 8–12, 2022
Paper No: ICONE29-93545
https://doi.org/10.1115/ICONE29-93545
View Paper titled, Verification and Validation of JMCT Monte Carlo Code in CPR1000
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Topics: China, Computer technology, Design, Fluence (Radiation measurement), Irradiation (Radiation exposure), Monte Carlo methods, Neutrons, Nuclear engineering, Nuclear power stations, Particulate matter
Proceedings Papers

Applying the PIRT Approach to the Meteorological Hazards Wind and Rainfall in Relation to Industrial Needs: Benefits and Lessons Learned

Tiphaine Le Morvan, Arièle Défossez, Mickaël Kreitz
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A016, August 8–12, 2022
Paper No: ICONE29-90907
https://doi.org/10.1115/ICONE29-90907
View Paper titled, Applying the PIRT Approach to the Meteorological Hazards Wind and Rainfall in Relation to Industrial Needs: Benefits and Lessons Learned
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Topics: Hazards, Meteorology, Nuclear power stations, Safety, Wind, Collaboration, Modeling, Natural phenomena, Nuclear engineers, Nuclear power
Proceedings Papers

Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6

Chang Zhang, Ruixiang Wang, Hui Guo, Hanyang Gu, Yao Xiao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A101, August 8–12, 2022
Paper No: ICONE29-92642
https://doi.org/10.1115/ICONE29-92642
View Paper titled, Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6
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Topics: Physics, Thermal hydraulics, Fuels, Temperature, Coolants, Light water reactors, Manufacturing, Simulation, Eigenvalues, Fuel rods
Proceedings Papers

Determination of Control Rod Position by Global Optimization Methods

Zhang Qian, Zhihong Liu, Jing Zhao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A100, August 8–12, 2022
Paper No: ICONE29-92637
https://doi.org/10.1115/ICONE29-92637
View Paper titled, Determination of Control Rod Position by Global Optimization Methods
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Topics: Algorithms, Optimization, Pressurized water reactors, Sensors, Computer software, Genetic algorithms, Inverse problems, Neutrons, Particle swarm optimization, Physics
Proceedings Papers

Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models

Jesse Fisher, Gary Mangham, Christopher Briggs, Guoqiang Wang, Baocheng Zhang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A061, August 8–12, 2022
Paper No: ICONE29-94476
https://doi.org/10.1115/ICONE29-94476
View Paper titled, Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models
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Topics: Boron, Feedback, Physics, Fuels, Linkages, Pressurized water reactors, Boiling, Boron compounds, Corrosion, Cycles
Proceedings Papers

Conceptual Multi-Physic Coupling Simulation on Transient Operations Of a He-Xe Cooled Mobile Nuclear Power Plant

Jiaolong Deng, Xiang Chai, Tengfei Zhang, Xiaojing Liu
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A036, August 8–12, 2022
Paper No: ICONE29-92247
https://doi.org/10.1115/ICONE29-92247
View Paper titled, Conceptual Multi-Physic Coupling Simulation on Transient Operations Of a He-Xe Cooled Mobile Nuclear Power Plant
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Topics: Nuclear power stations, Physics, Simulation, Transients (Dynamics)
Proceedings Papers

Development of JAEA Advanced Multi-Physics Analysis Platform for Nuclear Systems

Tomohiro Kamiya, Ayako Ono, Kenichi Tada, Hiroshi Akie, Yasunobu Nagaya, Hiroyuki Yoshida, Tomohiro Kawanishi
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A025, August 8–12, 2022
Paper No: ICONE29-91828
https://doi.org/10.1115/ICONE29-91828
View Paper titled, Development of JAEA Advanced Multi-Physics Analysis Platform for Nuclear Systems
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Topics: Fuels, Physics, Simulation, Thermal hydraulics, Two-phase flow
Proceedings Papers

Efficient Dynamic Monte Carlo Simulation in Multi-Physics Coupling Calculation

Danhua ShangGuan, Weihua Yan, Junxia Wei, Zhiming Gao, Yibing Chen, Zhicheng Ji
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A080, August 8–12, 2022
Paper No: ICONE29-93460
https://doi.org/10.1115/ICONE29-93460
View Paper titled, Efficient Dynamic Monte Carlo Simulation in Multi-Physics Coupling Calculation
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Topics: Monte Carlo methods, Physics, Simulation
Proceedings Papers

Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis

Zihao Guo, Guang Wang, Genghua Su, Xiuan Shi
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A036, August 8–12, 2022
Paper No: ICONE29-93256
https://doi.org/10.1115/ICONE29-93256
View Paper titled, Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis
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Topics: Design, Irradiation (Radiation exposure), Neutron flux, Physics, Water, Biomedicine, Isotopes, Cycles, Decontamination, Fuels
Proceedings Papers

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Qing Yang, Jianhua Xia, Xiaojing Liu, Qingquan Pan, Hui He, Tengfei Zhang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A038, August 8–12, 2022
Paper No: ICONE29-94534
https://doi.org/10.1115/ICONE29-94534
View Paper titled, 3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core
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Topics: Physics, Neutrons, Simulation, Computational fluid dynamics, Computer simulation, Conceptual design, Coolants, Design, Nuclear design, Optimization
Proceedings Papers

A Physics-Driven X-Ray Image Data Augmentation Method for Automated Threat Detection in Nuclear Facility Entrancement

Shuo Xu, Gang Chen, Weiwei Li, Xincheng Xiang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A041, August 8–12, 2022
Paper No: ICONE29-92402
https://doi.org/10.1115/ICONE29-92402
View Paper titled, A Physics-Driven X-Ray Image Data Augmentation Method for Automated Threat Detection in Nuclear Facility Entrancement
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Topics: Physics, X-rays
Proceedings Papers

Research on a Circuit Health Assessment Technology Combining Mechanism Knowledge and Data Driven Technology

Guilian Shi, Huang Xiaojin, Mo Changyu
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A007, August 8–12, 2022
Paper No: ICONE29-89387
https://doi.org/10.1115/ICONE29-89387
View Paper titled, Research on a Circuit Health Assessment Technology Combining Mechanism Knowledge and Data Driven Technology
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Topics: Circuits, Failure, Physics, Electronic equipment, Hardware, Design, Failure mechanisms, Nuclear power, Nuclear power stations, Time series
Proceedings Papers

Research on Optimization of Reload Startup Physics Tests in Sanmen Nuclear Power Plant

Jianfeng Shi, Qingxiang Yang, Lihua Wang, Lijiang Chen, Ang Li
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A016, August 8–12, 2022
Paper No: ICONE29-90570
https://doi.org/10.1115/ICONE29-90570
View Paper titled, Research on Optimization of Reload Startup Physics Tests in Sanmen Nuclear Power Plant
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Topics: Equilibrium (Physics), Leakage, Nuclear power stations, Optimization, Physics, Sensors, Economics , Design, Risk, Simulation
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

Development and Verification of Multigroup Cross Section Generation Module GroupXS in AXSP

Kui Hu, Xubo Ma, Xuan Ma, Chen Zhang, Guanqun Jia, Yixue Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A031, August 8–12, 2022
Paper No: ICONE29-91399
https://doi.org/10.1115/ICONE29-91399
View Paper titled, Development and Verification of Multigroup Cross Section Generation Module GroupXS in AXSP
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Topics: Approximation, Cross section (Physics), Errors, Intellectual property, Neutrons, Nuclear reactors, Nuclides, Physics
Proceedings Papers

A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core

Jie Liu, Chunyu Zhang, Zhihao Zheng, Jiesheng Min
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A073, August 8–12, 2022
Paper No: ICONE29-93008
https://doi.org/10.1115/ICONE29-93008
View Paper titled, A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core
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Topics: Fluid dynamics, Physics, Simulation, Computational fluid dynamics, Structural analysis, American Petroleum Institute, Computation, Computer simulation, Computer software, Computer-aided engineering
Proceedings Papers

Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling

Hongquan Liu, Yanan He, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A044, August 8–12, 2022
Paper No: ICONE29-91437
https://doi.org/10.1115/ICONE29-91437
View Paper titled, Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling
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Topics: Fuels, Heat transfer, Modeling, Physics, Process control, Computational fluid dynamics, Nuclear reactors, Simulation, Convection, Finite element analysis