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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

Paper No: ICONE29-93024

DOI: https://doi.org/10.1115/ICONE29-93024

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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

Paper No: ICONE29-93332

DOI: https://doi.org/10.1115/ICONE29-93332

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Topics: Manufacturing, Neutron sources, Safety, Storage, Transportation systems

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

Paper No: ICONE29-92816

DOI: https://doi.org/10.1115/ICONE29-92816

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Topics: Boron, Conformity assessment, Coolants, Cycles, Design, Neutron sources, Optimization, Pressurized water reactors, Radioactivity, Radioisotopes

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

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

Paper No: ICONE2020-16368

DOI: https://doi.org/10.1115/ICONE2020-16368

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Topics: Lithium, Coolants, Design, Fuel rods, Neutron sources, Chain, Combustion, Cycles, Fast neutron reactors, Fuels

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

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

Paper No: ICONE26-81276

DOI: https://doi.org/10.1115/ICONE26-81276

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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

Paper No: ICONE26-81520

DOI: https://doi.org/10.1115/ICONE26-81520

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Topics: Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutron sources, Neutrons, Nuclear decommissioning, Radioactivity, Reactor vessels, Reliability

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

Paper No: ICONE26-82390

DOI: https://doi.org/10.1115/ICONE26-82390

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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

Paper No: ICONE26-81329

DOI: https://doi.org/10.1115/ICONE26-81329

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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

Paper No: ICONE26-81595

DOI: https://doi.org/10.1115/ICONE26-81595

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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

Paper No: ICONE26-81392

DOI: https://doi.org/10.1115/ICONE26-81392

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Topics: Design, Neutron beams, Neutrons, Physics, Irradiation (Radiation exposure), Neutron sources, Contamination, Neutron generators, Boron, Cancer

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

Paper No: ICONE25-67386

DOI: https://doi.org/10.1115/ICONE25-67386

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Topics: Engineering prototypes, Neutron sources, Stress, Uranium

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

Paper No: ICONE25-66429

DOI: https://doi.org/10.1115/ICONE25-66429

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Topics: Computational methods, Cycles, Design, Engineering simulation, Equilibrium (Physics), Errors, Fluence (Radiation measurement), Geometry, Modeling, Neutron sources

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

Paper No: ICONE25-67573

DOI: https://doi.org/10.1115/ICONE25-67573

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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

Paper No: ICONE25-67580

DOI: https://doi.org/10.1115/ICONE25-67580

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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

Paper No: ICONE25-67384

DOI: https://doi.org/10.1115/ICONE25-67384

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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

Paper No: ICONE25-67988

DOI: https://doi.org/10.1115/ICONE25-67988

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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

Paper No: ICONE25-67291

DOI: https://doi.org/10.1115/ICONE25-67291

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Topics: Ceramics, Helium, Lithium, Design, China, Energy generation, Tokamaks, Vacuum, Vessels, Bridges (Structures)

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

Paper No: ICONE25-66518

DOI: https://doi.org/10.1115/ICONE25-66518

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Topics: Design, Uranium, Fuels, Engineering prototypes, Neutrons, Safety, China, Construction, Neutron sources, Nuclear power

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NARROW

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

Safety Analysis for Transportation of Activated Secondary Neutron Source Assembly

Optimization of the Tritium Production and Discharge in HPR1000

Calculation of Probability of Survival (POS) in Dynamic Systems Based on RMC Code

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

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

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

Preliminary Design of Unloading Device for MNSR LEU Conversion

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

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

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

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

The Measurement of Parameters of Zero Power Experiments Based on MNSR

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

A Research Reactor Core Design for Advance Neutron Source

Physical Design on PMNSR With LEU Core

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

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

Neutronic Analyses for CFETR With Modular Helium Cooled Lithium Ceramic Blanket

A New Low Enrichment Uranium Core Design of MNSR

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