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Proceedings Papers

Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement

Kai Tan, Ruihan Li, Jian Li, Jingang Liang, Ding She
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A053, August 8–12, 2022
Paper No: ICONE29-91659
DOI: https://doi.org/10.1115/ICONE29-91659
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Topics: Nuclides, Pressurized water reactors, Spent nuclear fuels, Density, Errors, Accuracy and precision, Fuels, Heat, Isotopes, Nuclear fission
Proceedings Papers

Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium

Ziling Zhou, Yu Wang, Jingni Guo, Feng Xie, Wenqian Li, Yanwei Wen, Bin Shan
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A039, August 8–12, 2022
Paper No: ICONE29-91275
DOI: https://doi.org/10.1115/ICONE29-91275
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Topics: Hydraulic conductivity, Very high temperature reactors, Fusion reactors, Hydrogen, Isotopes, Nuclear reactors, Coolants, Design, Diffusion (Physics), Engineering systems and industry applications
Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022
Paper No: ICONE29-89241
DOI: https://doi.org/10.1115/ICONE29-89241
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Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density
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
DOI: https://doi.org/10.1115/ICONE29-93256
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Topics: Design, Irradiation (Radiation exposure), Neutron flux, Physics, Water, Biomedicine, Isotopes, Cycles, Decontamination, Fuels
Proceedings Papers

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

Songyang Liu, Xiang Wang
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, V001T04A014, August 4–6, 2021
Paper No: ICONE28-65689
DOI: https://doi.org/10.1115/ICONE28-65689
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Topics: Isotopes, Neutrons, Optimization, Physics, Small modular reactors, Temperature, Cycles, Design, Fuels, China
Proceedings Papers

Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors

Ziling Zhou, Chuan Li, Nan Gui, Feng Xie, Yanwei Wen, Bin Shan, Jia Fu, Qunchao Fan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A016, August 4–6, 2021
Paper No: ICONE28-63539
DOI: https://doi.org/10.1115/ICONE28-63539
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Topics: Diffusion (Physics), Isotopes, Very high temperature reactors, Coolants, Graphite, Absorption, Desorption, Safety, Engineering prototypes, Fuels
Proceedings Papers

Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure

Simona Breidokaitė, Andrius Tidikas, Gediminas Stankūnas
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A031, August 4–5, 2020
Paper No: ICONE2020-16465
DOI: https://doi.org/10.1115/ICONE2020-16465
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Topics: Vacuum, Vessels, Cooling, Shells, Water, Isotopes, Neutrons, Radioisotopes, Stainless steel, Design
Proceedings Papers

Analysis of Major Group Structures Used for Nuclear Reactor Simulations

Marco Di Filippo, Jiri Krepel, Konstantin Mikityuk, Horst-Michael Prasser
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A029, July 22–26, 2018
Paper No: ICONE26-81445
DOI: https://doi.org/10.1115/ICONE26-81445
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Topics: Nuclear reactors, Simulation, Cross section (Physics), Resolution (Optics), Fast neutron reactors, Isotopes
Proceedings Papers

Influence of Xe-135 Dynamic Behavior on Core Operation Safety for a Molten Salt Reactor

Wu Jian-hui, Li Xiao-xiao, Hu Ji-feng, Chen Jin-gen, Yu Cheng-gang, Zou Chun-yan, Cai Xiang-zhou
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A050, July 22–26, 2018
Paper No: ICONE26-82352
DOI: https://doi.org/10.1115/ICONE26-82352
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Topics: Molten salt reactors, Safety, Neutrons, Fuels, Helium, Nuclear reactors, Absorption, Chain, Computational methods, Density
Proceedings Papers

Detection of Radon-Progeny and Other Alpha-Emitting Radionuclides in Air Using Tensioned Metastable Fluid Detectors

N. Boyle, B. Archambault, A. Hagen, C. Meert, R. P. Taleyarkhan
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A019, July 2–6, 2017
Paper No: ICONE25-66805
DOI: https://doi.org/10.1115/ICONE25-66805
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Topics: Fluids, Radioisotopes, Sensors, Temperature, Isotopes, Neutrons, Nuclear fission, Nuclear industry, Temperature effects, Alpha particles
Proceedings Papers

Proven Technologies for the Solidification of Complex Liquid Radioactive Waste (LRW): Global Case Studies of Applications and Disposal Options

Dennis Kelley
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A002, July 2–6, 2017
Paper No: ICONE25-66081
DOI: https://doi.org/10.1115/ICONE25-66081
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Topics: Radioactive wastes, Solidification, Nuclear power stations, Hazards, Isotopes, Nuclear decommissioning, Polymers, Storage, Warfare
Proceedings Papers

Analysis on Radioactive Gas Movement and Delay Status Before Release

Bo Nan Zhu
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A017, July 2–6, 2017
Paper No: ICONE25-66713
DOI: https://doi.org/10.1115/ICONE25-66713
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Topics: Delays, Activated carbon, Design, Dimensions, Flow (Dynamics), Computational methods, Design methodology, Isotopes, Nuclear fission, Nuclear power stations
Proceedings Papers

Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants

You Shi, Dong Ning, Yi-zhong Yang
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A026, July 2–6, 2017
Paper No: ICONE25-66256
DOI: https://doi.org/10.1115/ICONE25-66256
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Topics: Design, Neutrons, Nuclear power stations, Spent nuclear fuels, China, Density, Manufacturing, Spent fuel storage, Testing, Aluminum
Proceedings Papers

Effect of Spray System on in Containment Fission Product Washout During In-Vessel Release Phase

Khurram Mehboob, Mohammad. S. Aljohani
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A005, July 2–6, 2017
Paper No: ICONE25-66056
DOI: https://doi.org/10.1115/ICONE25-66056
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Topics: Containment, Nuclear fission, Sprays, Vessels, Drops, Absorption, Radioisotopes, Sensitivity analysis, Accidents, Computer simulation
Proceedings Papers

Research on Nickel-Plated Hydrogen-Absorption Device in Fuel Rod and Performance Testing

Zhou Qin, Li Jiwei, Dang Yu, Ding Yang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A041, July 2–6, 2017
Paper No: ICONE25-67112
DOI: https://doi.org/10.1115/ICONE25-67112
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Topics: Absorption, Fuel rods, Hydrogen, Nickel plating, Testing performance, Cladding systems (Building), Design, Pressure, Zirconium, Alloys
Proceedings Papers

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Bie Yewang, Li Huwei, Xiong Wenbin, Zhang Donghui, Wu Mingyu, Wang Xinzhe
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A118, July 2–6, 2017
Paper No: ICONE25-67994
DOI: https://doi.org/10.1115/ICONE25-67994
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Topics: China, Fast neutron reactors, Fuels, Manufacturing, Failure, Safety, Cladding systems (Building), Design, Heat transfer, Isotopes
Proceedings Papers

A New Method to Evaluate the Correlation Coefficients Between Nuclides in Uncertainty and Sensitivity Analysis

Xu Jia Yi, Ma Xu Bo, Shen Jing Wen, Liu Jia Yi, Chen Yi Xue
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A028, July 2–6, 2017
Paper No: ICONE25-66777
DOI: https://doi.org/10.1115/ICONE25-66777
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Topics: Nuclides, Sensitivity analysis, Uncertainty, Isotopes, Cross section (Physics), Density, Pressurized water reactors, Cycles, Fast neutron reactors, Nuclear engineering
Proceedings Papers

The Verification of SONG Library

Hua Bei, Jinkun Zhao, Qichang Chen, Shengyi Si
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A036, July 2–6, 2017
Paper No: ICONE25-66946
DOI: https://doi.org/10.1115/ICONE25-66946
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Topics: Absorption, Chemical kinetics, Cladding systems (Building), Electromagnetic scattering, Fuels, Isotopes, Molten salt reactors, Nuclear fission, Pressurized water reactors, Radiation scattering
Proceedings Papers

Development and Verification of Multi-Group Cross Section Process Code TXMAT for Fast Reactor RBEC-M Analysis

Ruomeng Qiu, Xubo Ma, Qian Xu, Jiayi Liu, Yixue Chen
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A015, July 2–6, 2017
Paper No: ICONE25-66550
DOI: https://doi.org/10.1115/ICONE25-66550
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Topics: Fast neutron reactors, Cross section (Physics), Absorption, Computer programming, Diffusion (Physics), Errors, Isotopes, Neutrons, Nuclear fission, S-matrix theory
Proceedings Papers

Molecular Dynamics Simulation of the Sputtering of Graphite due to Bombardment With Deuterium and Tritium in Fusion Environment

Qiang Zhao, Yang Li, Zheng Zhang, Xiaoping Ouyang
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A064, July 2–6, 2017
Paper No: ICONE25-67781
DOI: https://doi.org/10.1115/ICONE25-67781
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Topics: Graphite, Molecular dynamics simulation, Sputtering (Irradiation), Temperature, Hydrogen, Carbon, Isotopes, Molecular dynamics methods