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Proceedings Papers

Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting

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Rui Li, Shichang Liu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90902
https://doi.org/10.1115/ICONE29-90902
View Paper titled, Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting
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Topics: Nuclear reactors, Nuclides, Radiation (Physics), Neutrons, Cross section (Physics), Monte Carlo methods, Photons, Absorption, Databases, Elastic scattering
Proceedings Papers

The Study of a New Efficient Monte Carlo Method for Deep-Penetration Transport

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Tao Zhang, Zhihong Liu, Ding She, Jing Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A058, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92621
https://doi.org/10.1115/ICONE29-92621
View Paper titled, The Study of a New Efficient Monte Carlo Method for Deep-Penetration Transport
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Topics: Monte Carlo methods
Proceedings Papers

Efficient Dynamic Monte Carlo Simulation in Multi-Physics Coupling Calculation

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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
Publisher: American Society of Mechanical Engineers
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

Neutronics comparative analysis of fuel assemblies using CSG and DAGMC methods

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NingYan Sun, ShiChang Liu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A037, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91727
https://doi.org/10.1115/ICONE29-91727
View Paper titled, Neutronics comparative analysis of fuel assemblies using CSG and DAGMC methods
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Topics: Fuels, Geometry, Computer-aided design, Modeling, Particulate matter, Monte Carlo methods
Proceedings Papers

Verification and Validation of JMCT Monte Carlo Code in CPR1000

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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
Publisher: American Society of Mechanical Engineers
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

Study on Influencing Factors of Soil Sample Self-Absorption With Monte Carlo Method

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Erlei Ye, Chunxia Shen, Hongjie Nan
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A049, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92792
https://doi.org/10.1115/ICONE29-92792
View Paper titled, Study on Influencing Factors of Soil Sample Self-Absorption With Monte Carlo Method
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Topics: Absorption, Monte Carlo methods, Soil
Proceedings Papers

The Reconstruction of 3d Radiation Field Based on Sparse Measurement Data

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Xingwen Xie, Jiejin Cai, Zhihong Tang
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A098, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92608
https://doi.org/10.1115/ICONE29-92608
View Paper titled, The Reconstruction of 3d Radiation Field Based on Sparse Measurement Data
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Topics: Radiation (Physics), Interpolation, Errors, Matlab, Monte Carlo methods, Simulation
Proceedings Papers

Flux Rate Calculation and Analysis of the Integrated Small Pressurized Water Reactor Based on Monte Carlo Method

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Wen Yang, Fei Chao, Yun Tai, Longze Li
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, V001T04A011, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64448
https://doi.org/10.1115/ICONE28-64448
View Paper titled, Flux Rate Calculation and Analysis of the Integrated Small Pressurized Water Reactor Based on Monte Carlo Method
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Topics: Monte Carlo methods, Pressurized water reactors
Proceedings Papers

Using Monte Carlo Method and Adaptive Sampling to Estimate the Limit Surface

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Lixuan Zhang, Zhijian Zhang, He Wang, Yuhang Zhang, Dabin Sun
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A047, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64484
https://doi.org/10.1115/ICONE28-64484
View Paper titled, Using Monte Carlo Method and Adaptive Sampling to Estimate the Limit Surface
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Topics: Monte Carlo methods, Safety, Failure, Accidents, Cladding systems (Building), Fuels, Nuclear power stations, Risk, Simulation experiments, Simulation models
Proceedings Papers

Wall Materials Effects on Sheltered Indoor Doses From an SMR Hypothetical Accident Release

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Yamato Sugitatsu, Shripad T. Revankar
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62097
https://doi.org/10.1115/ICONE28-62097
View Paper titled, Wall Materials Effects on Sheltered Indoor Doses From an SMR Hypothetical Accident Release
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Topics: Accidents, Emergency management, Evacuations, Small modular reactors, Computer software, Coolants, Emergencies, Emergency response, Monte Carlo methods, Protective actions
Proceedings Papers

Effective Solid Angle Model and Monte Carlo Method: Improved Estimations to Measure Cosmic Muon Intensity at Sea Level in All Zenith Angles

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Junghyun Bae, Stylianos Chatzidakis, Robert Bean
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A011, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63444
https://doi.org/10.1115/ICONE28-63444
View Paper titled, Effective Solid Angle Model and Monte Carlo Method: Improved Estimations to Measure Cosmic Muon Intensity at Sea Level in All Zenith Angles
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Topics: Monte Carlo methods, Muons, Seas, Simulation
Proceedings Papers

Neutronic/Thermal-Hydraulic Coupling Analysis of Xi'an Pulsed Reactor Based on RMC and COBRA-TF

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Ruihan Li, Jianzhu Cao, Lipeng Wang, Xinyi Zhang, Xiaoyu Guo, Jingang Liang
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A059, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64623
https://doi.org/10.1115/ICONE28-64623
View Paper titled, Neutronic/Thermal-Hydraulic Coupling Analysis of Xi'an Pulsed Reactor Based on RMC and COBRA-TF
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Topics: Fuel rods, Monte Carlo methods, Neutrons, Physics, Simulation, Steady state, Temperature
Proceedings Papers

Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors

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Mohammad Alrwashdeh, Saeed A. Alameri
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, V001T05A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16838
https://doi.org/10.1115/ICONE2020-16838
View Paper titled, Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors
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Topics: Fuels, Particulate matter, Very high temperature reactors, Coating processes, Coatings, Cycles, Graphite, High temperature, Monte Carlo methods, Nuclear fuel cycle
Proceedings Papers

A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification

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Wankui Yang, Baoxin Yuan, Songbao Zhang, Haibing Guo, Yaoguang Liu, Li Deng
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A032, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81709
https://doi.org/10.1115/ICONE26-81709
View Paper titled, A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification
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Topics: Computational methods, Neutrons, Geometry, Modeling, Monte Carlo methods, China, Cross section (Physics), Finishes, Slabs, Tin
Proceedings Papers

A Monte Carlo Method for Simulating Stochastic Neutron Fields in Criticality Transients

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Qi Xu, Zhe Wang, Gang Xiao
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A028, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81595
https://doi.org/10.1115/ICONE26-81595
View Paper titled, A Monte Carlo Method for Simulating Stochastic Neutron Fields in Criticality Transients
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Topics: Monte Carlo methods, Neutrons, Transients (Dynamics), Probability, Simulation, Statistical distributions, Accidents, Neutron sources, Nuclear fission
Proceedings Papers

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

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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

Study on Variation of HPGE Detector Dead Layer Thickness and its Effect on the Measurements of the Detector Response and Samples Characterization Using Monte Carlo Simulation

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K. Abd El Gawad, Yushou Song
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A038, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82098
https://doi.org/10.1115/ICONE26-82098
View Paper titled, Study on Variation of HPGE Detector Dead Layer Thickness and its Effect on the Measurements of the Detector Response and Samples Characterization Using Monte Carlo Simulation
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Topics: Sensors, Simulation, Germanium, Monte Carlo methods, Photons, Absorption, Modeling, Optimization, Simulation models
Proceedings Papers

Application of the Dynamic Rod Worth Measurement Method on WWER

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Wenbo Zhao, Zhumin Jiang, Liangzi Wang, Chenlin Wang, Yingrui Yu, Zhaohu Gong, Minxiao Zhong, Tongxian Liu, Hongzhi Xiang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A003, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81055
https://doi.org/10.1115/ICONE26-81055
View Paper titled, Application of the Dynamic Rod Worth Measurement Method on WWER
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Topics: Boron, Dynamics (Mechanics), Geometry, Monte Carlo methods, Neutrons, Nuclear power stations, Pressurized water reactors, Sensors, Shapes, Spacetime
Proceedings Papers

The Radiation Protection Design of PWR Spent Fuel Dry Storage Facility

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Liming Huang, Shouhai Yang, Jie Liu
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81552
https://doi.org/10.1115/ICONE26-81552
View Paper titled, The Radiation Protection Design of PWR Spent Fuel Dry Storage Facility
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Topics: Design, Pressurized water reactors, Radiation (Physics), Spent nuclear fuels, Storage, Safety, Spent fuel storage, China, Construction, Monte Carlo methods
Proceedings Papers

The Dose Constraint Calculation of High Radioactivity Level Waste Canister Surface

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Bo Yang, Qianglin Wei, Hexi Wu, Xujia Luo, Yibao Liu
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82056
https://doi.org/10.1115/ICONE26-82056
View Paper titled, The Dose Constraint Calculation of High Radioactivity Level Waste Canister Surface
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Topics: Containers, Monte Carlo methods, Neutrons, Packaging, Photons, Radiation (Physics), Radioactive wastes, Radioactivity, Safety, Tunnels