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Proceedings Papers

Investigation on Thermal Conductivity and Viscosity of Thin Water Film by Molecular Dynamics Simulation

Lu Jin, Leping Zhou
Proc. ASME. MNHMT2019, ASME 2019 6th International Conference on Micro/Nanoscale Heat and Mass Transfer, V001T10A005, July 8–10, 2019
Paper No: MNHMT2019-4087
DOI: https://doi.org/10.1115/MNHMT2019-4087
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Topics: Molecular dynamics simulation, Nanoscale phenomena, Thermal conductivity, Thin films, Viscosity, Water
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

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

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
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