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Proceedings Papers

Optimization of the Tritium Production and Discharge in HPR1000

Pengtao Fu, Mingliang Dai
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A033, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92816
https://doi.org/10.1115/ICONE29-92816
View Paper titled, Optimization of the Tritium Production and Discharge in HPR1000
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Topics: Boron, Conformity assessment, Coolants, Cycles, Design, Neutron sources, Optimization, Pressurized water reactors, Radioactivity, Radioisotopes
Proceedings Papers

The Study of Removal of Secondary Neutron Source of HPR-1000

Huiwen Xiao, Xiang Li, Guoming Liu, Yicheng Zhang, Zeng Shao, Min Xu, Xuan Yi, Haifeng Yang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A061, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93024
https://doi.org/10.1115/ICONE29-93024
View Paper titled, The Study of Removal of Secondary Neutron Source of HPR-1000
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Topics: Neutron sources, Spent nuclear fuels
Proceedings Papers

Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly

Nanfeng Cao, Shouhai Yang, Enfei Xie, Shunping Jing
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A077, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93332
https://doi.org/10.1115/ICONE29-93332
View Paper titled, Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly
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Topics: Manufacturing, Neutron sources, Safety, Storage, Transportation systems
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

Neutronic Study on Conceptual Lithium Fluoride Salt Cooled Fusion Driven System for Actinide Transmutation

Feryantama Putra
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, V001T05A011, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16368
https://doi.org/10.1115/ICONE2020-16368
View Paper titled, Neutronic Study on Conceptual Lithium Fluoride Salt Cooled Fusion Driven System for Actinide Transmutation
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Topics: Lithium, Coolants, Design, Fuel rods, Neutron sources, Chain, Combustion, Cycles, Fast neutron reactors, Fuels
Proceedings Papers

Virtual Prototyping and Simulation of Robotic Devices and Maintenance Procedures for Remote Handling Activities in the Access Cell of DONES

Stefano Papa, Giuseppe di Gironimo, Federica Casoria, Gioacchino Micciché
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A016, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82390
https://doi.org/10.1115/ICONE26-82390
View Paper titled, Virtual Prototyping and Simulation of Robotic Devices and Maintenance Procedures for Remote Handling Activities in the Access Cell of DONES
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Topics: Maintenance, Robotics, Simulation, Kinematics, Chain, Collaboration, Conceptual design, Cranes, Degrees of freedom, End effectors
Proceedings Papers

Neutronic Study on a New Concept of Accelerator Driven Subcritical System in China

Jinyang Li, Long Gu, Cunfeng Yao, Dawei Wang, Tianji Peng, Yanlei Zhu
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A007, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81329
https://doi.org/10.1115/ICONE26-81329
View Paper titled, Neutronic Study on a New Concept of Accelerator Driven Subcritical System in China
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Topics: China, Cycles, Design, Doppler effect, Flow (Dynamics), Gravity (Force), Heavy metals, Neutron sources, Neutrons, Physics
Proceedings Papers

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

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

Physics Design of Special Epithermal Neutron Beam Based on Multi D-D Reaction Neutron Tubes

Yi Yang, Yiguo Li, Bin Zhao
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81392
https://doi.org/10.1115/ICONE26-81392
View Paper titled, Physics Design of Special Epithermal Neutron Beam Based on Multi D-D Reaction Neutron Tubes
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Topics: Design, Neutron beams, Neutrons, Physics, Irradiation (Radiation exposure), Neutron sources, Contamination, Neutron generators, Boron, Cancer
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
Publisher: American Society of Mechanical Engineers
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

Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems

Run Luo, Pengfei Wang, Xinyu Wei, Shripad T. Revankar, Fuyu Zhao
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A004, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81276
https://doi.org/10.1115/ICONE26-81276
View Paper titled, Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems
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Topics: Thermal hydraulics, Steady state, Transients (Dynamics), Computer simulation, Dynamic models, Engineering simulation, Fuels, Neutron sources, Neutrons, Simulation
Proceedings Papers

Preliminary Design of Unloading Device for MNSR LEU Conversion

Hao Qian, Li Yiguo, Peng Dan, Wu Xiaobo, Lu Jin, Hong Jingyan, Zhang Jinhua, Wang Mengjiao
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81520
https://doi.org/10.1115/ICONE26-81520
View Paper titled, Preliminary Design of Unloading Device for MNSR LEU Conversion
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Topics: Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutron sources, Neutrons, Nuclear decommissioning, Radioactivity, Reactor vessels, Reliability
Proceedings Papers

The Preliminary Shielding Analysis of CAP1400 Based on JMCT-S Code

Yan Zhou, Zheng Zheng, Qiliang Mei
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A007, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66429
https://doi.org/10.1115/ICONE25-66429
View Paper titled, The Preliminary Shielding Analysis of CAP1400 Based on JMCT-S Code
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Topics: Computational methods, Cycles, Design, Engineering simulation, Equilibrium (Physics), Errors, Fluence (Radiation measurement), Geometry, Modeling, Neutron sources
Proceedings Papers

A New Low Enrichment Uranium Core Design of MNSR

Wang Mengjiao, Li Yiguo, Wu Xiaobo, Peng Dan, Hong Jingyan, Hao Qian, Zhang Jinhua, Lu Jin
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A012, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66518
https://doi.org/10.1115/ICONE25-66518
View Paper titled, A New Low Enrichment Uranium Core Design of MNSR
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Topics: Design, Uranium, Fuels, Engineering prototypes, Neutrons, Safety, China, Construction, Neutron sources, Nuclear power
Proceedings Papers

The Measurement of Parameters of Zero Power Experiments Based on MNSR

Hong Jingyan, Peng Dan, Wu Xiaobo, Lu Jin, Li Yiguo
Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T04A035, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67386
https://doi.org/10.1115/ICONE25-67386
View Paper titled, The Measurement of Parameters of Zero Power Experiments Based on MNSR
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Topics: Engineering prototypes, Neutron sources, Stress, Uranium
Proceedings Papers

A Research Reactor Core Design for Advance Neutron Source

Zeyun Wu
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A059, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67573
https://doi.org/10.1115/ICONE25-67573
View Paper titled, A Research Reactor Core Design for Advance Neutron Source
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Topics: Design, Neutron sources, Heat flux, Brightness (Photometry), Cycles, Fuels, Neutrons, Thermal energy
Proceedings Papers

Physical Design on PMNSR With LEU Core

Wu Xiaobo, Peng Dan, Hong Jingyan, Lu Jin, Hao Qian
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A060, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67580
https://doi.org/10.1115/ICONE25-67580
View Paper titled, Physical Design on PMNSR With LEU Core
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Topics: Design, Fuels, Neutron flux, Uranium, Coolants, Engineering prototypes, Error analysis, Irradiation (Radiation exposure), Manufacturing, Neutron sources
Proceedings Papers

Physics Design of Epi-Thermal Neutron Beam for BNCT Based on C-MNSR

Peng Dan, Wu Xiaobo, Lu Jin, Hao Qian, Hong Jingyan, Li Yiguo
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A054, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67384
https://doi.org/10.1115/ICONE25-67384
View Paper titled, Physics Design of Epi-Thermal Neutron Beam for BNCT Based on C-MNSR
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Topics: Design, Neutron beams, Physics, Fuels, Neutrons, Cancer, Uranium, Boron, Contamination, Density
Proceedings Papers

Loading Scheme Research of Small Modular Sodium Cooled Reactor in a Factory

Hu Xiao, Chen Xiao Liang
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A056, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67988
https://doi.org/10.1115/ICONE25-67988
View Paper titled, Loading Scheme Research of Small Modular Sodium Cooled Reactor in a Factory
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Topics: Sodium, Sensors, Neutron sources, China, Fuels, Reactor vessels, Simulation, Chemical properties, Construction, Fast neutron reactors
Proceedings Papers

Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket

Kun Xu, Minyou Ye, Yuntao Song, Mingzhun Lei, Shifeng Mao
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A035, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67291
https://doi.org/10.1115/ICONE25-67291
View Paper titled, Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket
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Topics: Ceramics, Helium, Lithium, Design, China, Energy generation, Tokamaks, Vacuum, Vessels, Bridges (Structures)