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Proceedings Papers

High Efficient Mineralization of Cesium in Waste Liquid by Hydrothermal Method

Kai Gao, Wendong Feng, Xiaojun Yan, Xiaobin Guo, Xiaoyan Cui, Xiliang Guo
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A009, August 8–12, 2022
Paper No: ICONE29-90716
DOI: https://doi.org/10.1115/ICONE29-90716
View Paper titled, High Efficient Mineralization of Cesium in Waste Liquid by Hydrothermal Method
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Topics: Aluminum, Cements (Adhesives), Exhaust systems, Glass, High temperature, Ion exchange, Nuclear fuel cycle, Phase transition temperature, Raw materials, Sewage
Proceedings Papers

Thermal Safety Margin Calculation of the MP-2 Experiment in the Advanced Test Reactor

Grant L. Hawkes
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A030, August 4–5, 2020
Paper No: ICONE2020-16592
DOI: https://doi.org/10.1115/ICONE2020-16592
View Paper titled, Thermal Safety Margin Calculation of the MP-2 Experiment in the Advanced Test Reactor
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Topics: Fuels, Irradiation (Radiation exposure), Safety, Cycles, Plates (structures), Transients (Dynamics), Heat, Aluminum, Finite element analysis, Thermal analysis
Proceedings Papers

Structure Topology Optimization Design and Shock Resistance Study on Nuclear Power Safety DCS Cast Aluminum Cabinet

Wang Dongwei, Liu Mingxing, Wu Xiao, Yan Hao, Wu Zhiqiang
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, V001T06A024, August 4–5, 2020
Paper No: ICONE2020-16774
DOI: https://doi.org/10.1115/ICONE2020-16774
View Paper titled, Structure Topology Optimization Design and Shock Resistance Study on Nuclear Power Safety DCS Cast Aluminum Cabinet
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Topics: Aluminum, Design, Nuclear power, Nuclear power stations, Optimization, Safety, Shock (Mechanics), Topology
Proceedings Papers

Measuring Effects of Radiation on Precipitates in Aluminum 7075-T6 Using Differential Scanning Calorimetry

Rachel C. Connick, Charles A. Hirst, Penghui Cao, Kangpyo So, R. Scott Kemp, Michael P. Short
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A090, July 22–26, 2018
Paper No: ICONE26-82457
DOI: https://doi.org/10.1115/ICONE26-82457
View Paper titled, Measuring Effects of Radiation on Precipitates in Aluminum 7075-T6 Using Differential Scanning Calorimetry
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Topics: Aluminum, Differential scanning calorimetry, Radiation effects, Irradiation (Radiation exposure), Damage, Thermal analysis, Alpha particles, Aluminum alloys, Bridges (Structures), Helium
Proceedings Papers

Thermal Analysis Safety Margins Using ABAQUS for the MP-2 Experiment in the Advanced Test Reactor

Grant L. Hawkes, Douglas S. Crawford, Gregory K. Housley
Proc. ASME. NUCLRF2018, ASME 2018 Nuclear Forum, V001T04A003, June 24–28, 2018
Paper No: NUCLRF2018-7600
DOI: https://doi.org/10.1115/NUCLRF2018-7600
View Paper titled, Thermal Analysis Safety Margins Using ABAQUS for the MP-2 Experiment in the Advanced Test Reactor
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Topics: Safety, Thermal analysis, Fuels, Irradiation (Radiation exposure), Water, Aluminum, Finite element analysis, Plates (structures), Coolants, Finite element model
Proceedings Papers

Technology Development on Reactor Dismantling and Investigation of Contamination in FUGEN

Goro Soejima, Hiroki Iwai, Yasuyuki Nakamura, Hirokazu Hayashi, Haruhiko Kadowaki, Hiroyuki Mizui, Kazuya Sano
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A019, July 2–6, 2017
Paper No: ICONE25-66950
DOI: https://doi.org/10.1115/ICONE25-66950
View Paper titled, Technology Development on Reactor Dismantling and Investigation of Contamination in FUGEN
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Topics: Contamination, Technology development, Laser cutting, Cutting, Nuclear decommissioning, Water, Pipes, Zirconium alloys, Aluminum, Boiling
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
View Paper titled, Qualification Requirements Design for Neutron Absorber Plate for Spent Fuel Racks in Domestic Nuclear Power Plants
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Topics: Design, Neutrons, Nuclear power stations, Spent nuclear fuels, China, Density, Manufacturing, Spent fuel storage, Testing, Aluminum
Proceedings Papers

Composite Versus Dispersed Accident Tolerant Nuclear Fuels

Jayangani Ranasinghe, Barbara Szpunar, Ericmoore Jossou, Linu Malakkal, Jerzy A. Szpunar
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A056, July 2–6, 2017
Paper No: ICONE25-67478
DOI: https://doi.org/10.1115/ICONE25-67478
View Paper titled, Composite Versus Dispersed Accident Tolerant Nuclear Fuels
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Topics: Accidents, Composite materials, Nuclear fuels, Fuels, Temperature, Temperature gradient, Thermal conductivity, Aluminum, Approximation, Cracking (Materials)
Proceedings Papers

The Chemistry Experience Summary During the Engineering Commissioning Period of Fujian Ningde Nuclear Power Plant

Heng Liu, Yue Chen, Fuping Li, Hui Liu, Shunlong Yang
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, V001T01A029, July 2–6, 2017
Paper No: ICONE25-67040
DOI: https://doi.org/10.1115/ICONE25-67040
View Paper titled, The Chemistry Experience Summary During the Engineering Commissioning Period of Fujian Ningde Nuclear Power Plant
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Topics: Chemistry, Nuclear power stations, Construction, Instrumentation, Maintenance, Water chemistry, Water pollution, Aluminum, Design, Fuels
Proceedings Papers

Flow Testing and Analysis of the FSP-1 Experiment

Grant L. Hawkes, Warren F. Jones, Wade Marcum, Aaron Weiss, Trevor Howard
Proc. ASME. NUCLRF2017, ASME 2017 Nuclear Forum, V009T03A005, June 26–30, 2017
Paper No: NUCLRF2017-3639
DOI: https://doi.org/10.1115/NUCLRF2017-3639
View Paper titled, Flow Testing and Analysis of the FSP-1 Experiment
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Topics: Flow (Dynamics), Testing, Fuels, Plates (structures), Uranium, Alloys, Aluminum, Molybdenum, Orifices, Pressure
Proceedings Papers

Effects of Cladding Material on Irradiation Performance of Monolithic Mini-Plates

Hakan Ozaltun
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A009, June 26–30, 2016
Paper No: ICONE24-60120
DOI: https://doi.org/10.1115/ICONE24-60120
View Paper titled, Effects of Cladding Material on Irradiation Performance of Monolithic Mini-Plates
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Topics: Cladding systems (Building), Irradiation (Radiation exposure), Plates (structures), Fuels, Stress, Aluminum, Alloys, Density, Diffusion (Physics), Displacement
Proceedings Papers

Oxygen Used as an Oxidizer in Acid In-Situ Leach Uranium: From Theory to Practice

Wensheng Liao, Yahui Tan, Limin Wang, Jianhua Li
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A010, June 26–30, 2016
Paper No: ICONE24-60126
DOI: https://doi.org/10.1115/ICONE24-60126
View Paper titled, Oxygen Used as an Oxidizer in Acid In-Situ Leach Uranium: From Theory to Practice
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Topics: Oxygen, Uranium, Pressure, Aluminum, Minerals, Precipitation, Hydrogen, Iron, Testing
Proceedings Papers

Electron Beam Weldability of AA6061-T6 Aluminum Straps for U-Mo Follower Fuel Assembly Manufacturing

Soo-sung Kim, Yong-jin Jeong, Jong-man Park, Yoon-sang Lee, Chong-tak Lee
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A002, June 26–30, 2016
Paper No: ICONE24-60041
DOI: https://doi.org/10.1115/ICONE24-60041
View Paper titled, Electron Beam Weldability of AA6061-T6 Aluminum Straps for U-Mo Follower Fuel Assembly Manufacturing
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Topics: Aluminum, Cathode ray oscilloscopes, Electron beams, Fuels, Manufacturing, Exploding wires, Die cutting, Fillers (Materials), Shearing (Deformation), Welding
Proceedings Papers

Cryogenic Hydrogen Cooling of Heated Moderator Vessel

Per Nilsson, Mateusz Pucilowski, Yannick Bessler
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A021, June 26–30, 2016
Paper No: ICONE24-60722
DOI: https://doi.org/10.1115/ICONE24-60722
View Paper titled, Cryogenic Hydrogen Cooling of Heated Moderator Vessel
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Topics: Cooling, Hydrogen, Vessels, Temperature, Aluminum, Computational fluid dynamics, Design, Neutrons, Engineering simulation, Fluids
Proceedings Papers

Thermal Analysis of the FSP-1 Experiment in the Advanced Test Reactor

Grant L. Hawkes, Nicolas E. Woolstenhulme
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A059, June 26–30, 2016
Paper No: ICONE24-60752
DOI: https://doi.org/10.1115/ICONE24-60752
View Paper titled, Thermal Analysis of the FSP-1 Experiment in the Advanced Test Reactor
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Topics: Thermal analysis, Safety, Fuels, Plates (structures), Coolants, Uranium, Alloys, Aluminum, Canals, Cooling
Proceedings Papers

Effects of the Foil Centering on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

Jill Wright, Hakan Ozaltun
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T03A003, June 28–July 2, 2015
Paper No: NUCLRF2015-49462
DOI: https://doi.org/10.1115/NUCLRF2015-49462
View Paper titled, Effects of the Foil Centering on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates
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Topics: Alloys, Irradiation (Radiation exposure), Plates (structures), Fuels, Cladding systems (Building), Cooling, Engineering simulation, Manufacturing, Simulation, Warping
Proceedings Papers

Effects of the Shape of the Foil Corners on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

Hakan Ozaltun, Pavel Medvedev
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T03A001, June 28–July 2, 2015
Paper No: NUCLRF2015-49284
DOI: https://doi.org/10.1115/NUCLRF2015-49284
View Paper titled, Effects of the Shape of the Foil Corners on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates
Click here to open pdf in another window PDF for Effects of the Shape of the Foil Corners on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates
Topics: Alloys, Corners (Structural elements), Irradiation (Radiation exposure), Plates (structures), Shapes, Fuels, Manufacturing, Stress, Engineering simulation, Simulation
Proceedings Papers

Experimental Investigation of Nanotubes Utilization as a Nuclear Fuel Matrix Additive

Jan Varmuza, Karel Katovsky, Jiri Skalicka, Stepan Foral, Jitka Matejkova
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A070, July 7–11, 2014
Paper No: ICONE22-31260
DOI: https://doi.org/10.1115/ICONE22-31260
View Paper titled, Experimental Investigation of Nanotubes Utilization as a Nuclear Fuel Matrix Additive
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Topics: Nanotubes, Nuclear fuels, Carbon, Nanomaterials, Neutrons, Aluminum, Cladding systems (Building), Composite materials, Fuels, Materials properties
Proceedings Papers

Prospect of MAO Technology Application in Nuclear Power Industry

Zheng Zhao, Beibei Feng, Xingtuan Yang, Yanfei Sun
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A019, July 29–August 2, 2013
Paper No: ICONE21-15435
DOI: https://doi.org/10.1115/ICONE21-15435
View Paper titled, Prospect of MAO Technology Application in Nuclear Power Industry
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Topics: Nuclear industry, Alloys, Aluminum, Cladding systems (Building), Corrosion, Fuels, Nuclear reactors, Accidents, Aerospace industry, Aviation
Proceedings Papers

Monte Carlo Simulation Compared With Classic Deterministic Solutions for Neutron Transport and Diffusion

Zafar Ullah Koreshi, Sadaf Siddiq
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 251-258, May 17–21, 2010
Paper No: ICONE18-29971
DOI: https://doi.org/10.1115/ICONE18-29971
View Paper titled, Monte Carlo Simulation Compared With Classic Deterministic Solutions for Neutron Transport and Diffusion
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Topics: Diffusion (Physics), Neutrons, Simulation, Slabs, Electromagnetic scattering, Geometry, Radiation scattering, Scattering (Physics), Aluminum, Eigenfunctions