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Proceedings Papers

Investigation of Swelling Behaviors of U-10Zr Metallic Fuel in the Low Temperature Regime via a Combined Thermo-Mechanical and Rate Theory Analysis

Zhengyu Qian, Di Yun
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A053, August 8–12, 2022
Paper No: ICONE29-92285
DOI: https://doi.org/10.1115/ICONE29-92285
View Paper titled, Investigation of Swelling Behaviors of U-10Zr Metallic Fuel in the Low Temperature Regime via a Combined Thermo-Mechanical and Rate Theory Analysis
Click here to open pdf in another window PDF for Investigation of Swelling Behaviors of U-10Zr Metallic Fuel in the Low Temperature Regime via a Combined Thermo-Mechanical and Rate Theory Analysis
Topics: Fuels, Low temperature, Thermomechanics, Uranium, Zirconium
Proceedings Papers

Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor

Yutai Cai, Wenzhong Zhou, Long Gu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A041, August 8–12, 2022
Paper No: ICONE29-91817
DOI: https://doi.org/10.1115/ICONE29-91817
View Paper titled, Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor
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Topics: Fast neutron reactors, Fuels, Modeling, Thermomechanics, Uranium
Proceedings Papers

Numerical Simulation Analysis of Silicon Carbide Whiskers Doped Uranium Dioxide Composite Fuel for High Thermal Conductivity

Linyuan Lu, LiHua Guo, Yajuan Zhong, Feng Zhang, Jun Lin
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A040, August 8–12, 2022
Paper No: ICONE29-91804
DOI: https://doi.org/10.1115/ICONE29-91804
View Paper titled, Numerical Simulation Analysis of Silicon Carbide Whiskers Doped Uranium Dioxide Composite Fuel for High Thermal Conductivity
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Topics: Composite materials, Computer simulation, Fuels, Silicon, Temperature distribution, Thermal conductivity, Thermal resistance, Uranium, Finite element methods, Accidents
Proceedings Papers

Active Interrogation of Highly Enriched Uranium in the Suitcase by Using NG-9 Neutron Generator

Guang-Yu Shi, Shi-Wei Jing
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A015, August 8–12, 2022
Paper No: ICONE29-89597
DOI: https://doi.org/10.1115/ICONE29-89597
View Paper titled, Active Interrogation of Highly Enriched Uranium in the Suitcase by Using NG-9 Neutron Generator
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Topics: Neutron flux, Neutron generators, Uranium
Proceedings Papers

Preliminary Design and Neutronics Analysis for a Medium Temperature Heat Pipe Cooled Reactor

Sina Li, Binhuo Yan, Guojun Tang, Donghong Peng, Hongzhi Lu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A017, August 8–12, 2022
Paper No: ICONE29-89659
DOI: https://doi.org/10.1115/ICONE29-89659
View Paper titled, Preliminary Design and Neutronics Analysis for a Medium Temperature Heat Pipe Cooled Reactor
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Topics: Design, Heat pipes, Safety, Temperature, Uranium
Proceedings Papers

Comparison of the Powderization Effect of Non-Equilibrium Plasma Oxidation and Thermochemical Oxidation Powders of Uranium Dioxide Solids for Actinide Analysis

Zhuoran Ma, Takaharu Tatsuno, Yoshiya Homma, Kenji Konashi, Katsuya Suzuki, Tatsuya Suzuki
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A010, August 8–12, 2022
Paper No: ICONE29-90894
DOI: https://doi.org/10.1115/ICONE29-90894
View Paper titled, Comparison of the Powderization Effect of Non-Equilibrium Plasma Oxidation and Thermochemical Oxidation Powders of Uranium Dioxide Solids for Actinide Analysis
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Topics: Equilibrium (Physics), Oxidation, Plasmas (Ionized gases), Solids, Uranium
Proceedings Papers

The Location of Spent Fuel Pins in Heavy Water Research Reactor in the Spent Fuel Pool

Jin Lu, Peng Nie, Ren Ren, Yaping Guo, Qi Wang, Xinwang Zhang, Lijun Zhang
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A013, August 8–12, 2022
Paper No: ICONE29-91465
DOI: https://doi.org/10.1115/ICONE29-91465
View Paper titled, The Location of Spent Fuel Pins in Heavy Water Research Reactor in the Spent Fuel Pool
Click here to open pdf in another window PDF for The Location of Spent Fuel Pins in Heavy Water Research Reactor in the Spent Fuel Pool
Topics: Fuels, Pins (Engineering), Spent nuclear fuels, Uranium, Water
Proceedings Papers

Levelized Cost of Electricity Evaluation Methodology Applied to High-Burnup 18 and 24-Month Fuel Cycles

David L. Stucker, Jeff Norrell, Ho Lam, Fausto Franceschini
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A019, August 4–6, 2021
Paper No: ICONE28-66589
DOI: https://doi.org/10.1115/ICONE28-66589
View Paper titled, Levelized Cost of Electricity Evaluation Methodology Applied to High-Burnup 18 and 24-Month Fuel Cycles
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Topics: Cycles, Fuel management, Fuels, Uranium
Proceedings Papers

A Sodium-Cooled Thermal-Spectrum Fission Battery

Patrick J. McDaniel, Charles Forsberg
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, V001T04A015, August 4–6, 2021
Paper No: ICONE28-65765
DOI: https://doi.org/10.1115/ICONE28-65765
View Paper titled, A Sodium-Cooled Thermal-Spectrum Fission Battery
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Topics: Batteries, Nuclear fission, Sodium, Heat, Neutrons, Uranium, Carbon, Data centers, Design, Economics
Proceedings Papers

Summary of the Practice of Clearance of Uranium-Containing Calcium Fluoride Slags in China’s Nuclear Facilities

Jing Jiang, Qiang Lei, Chen Xu, Zhaowen Zhu, Chunyan Xu, Shijun Wang, Xiaolong Li, Min Zhang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A010, August 4–6, 2021
Paper No: ICONE28-64357
DOI: https://doi.org/10.1115/ICONE28-64357
View Paper titled, Summary of the Practice of Clearance of Uranium-Containing Calcium Fluoride Slags in China’s Nuclear Facilities
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Topics: Clearances (Engineering), Nuclear power stations, Slags, Uranium
Proceedings Papers

Uranium Radioactivity Measurement for Low-Level Wastewater Based on Ultra-Low Level Liquid Scintillation Analyzer

Jinxu Lv, Ning Lv, Huiping Guo, Zeting Hu, Geng Song, Yinying Cai, Heling Zhang, Daji Li
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A013, August 4–5, 2020
Paper No: ICONE2020-16143
DOI: https://doi.org/10.1115/ICONE2020-16143
View Paper titled, Uranium Radioactivity Measurement for Low-Level Wastewater Based on Ultra-Low Level Liquid Scintillation Analyzer
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Topics: Radiation measurement, Radioactivity, Sewage, Uranium
Proceedings Papers

Synergetic Oxidation in Alkaline In-Situ Leaching Uranium: A Preliminary Case Study

Wensheng Liao, Weimin Que, Liming Wang, Zhiming Du
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, V001T05A007, August 4–5, 2020
Paper No: ICONE2020-16200
DOI: https://doi.org/10.1115/ICONE2020-16200
View Paper titled, Synergetic Oxidation in Alkaline In-Situ Leaching Uranium: A Preliminary Case Study
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Topics: In situ processing (Mining), Oxidation, Uranium
Proceedings Papers

A Mathematical Link Between the Natural Energy of Stars and Fission

Brenda K. Krkosska Bayles
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A001, July 22–26, 2018
Paper No: ICONE26-81093
DOI: https://doi.org/10.1115/ICONE26-81093
View Paper titled, A Mathematical Link Between the Natural Energy of Stars and Fission
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Topics: Nuclear fission, Flow (Dynamics), Particulate matter, Protons, Chain, Nuclear engineering, Uranium
Proceedings Papers

Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density

Shogo Noda, Sukarman Sukarman, Akifumi Yamaji, Tetsuo Takei, Takanari Fukuda, Arisa Ayukawa
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A011, July 22–26, 2018
Paper No: ICONE26-81501
DOI: https://doi.org/10.1115/ICONE26-81501
View Paper titled, Core Design Study of Super FBR With Multi-Axial Fuel Shuffling and Different Coolant Density
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Topics: Coolants, Density, Design, Fuels, Breeder reactors, Collisions (Physics), Neutron flux, Neutrons, Probability, Temperature
Proceedings Papers

Revamping of a Graduate Radiochemistry Course for Nuclear Forensics Applications

Adam Drescher, Brandon De Luna, Marjolein Pasman, Derek Haas, Sheldon Landsberger
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A037, July 22–26, 2018
Paper No: ICONE26-81593
DOI: https://doi.org/10.1115/ICONE26-81593
View Paper titled, Revamping of a Graduate Radiochemistry Course for Nuclear Forensics Applications
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Topics: Forensic sciences, Gamma ray spectrometry, Graduate students, Calibration, Chemistry, Equilibrium (Physics), Explosions, Half-life, Ion exchange, Nuclear engineering
Proceedings Papers

CANDU 6 Accident Analysis Using RELAP/SCDAPSIM With the Integrated Uncertainty Package

Roxana-Mihaela Nistor-Vlad, Daniel Dupleac, Ilie Prisecaru, Chris Allison, M. Perez-Ferragut, Judith Hohorst
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A076, July 22–26, 2018
Paper No: ICONE26-82241
DOI: https://doi.org/10.1115/ICONE26-82241
View Paper titled, CANDU 6 Accident Analysis Using RELAP/SCDAPSIM With the Integrated Uncertainty Package
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Topics: Accidents, Uncertainty, Uncertainty analysis, Light water reactors, Nuclear reactors, Heat, Nuclear power stations, Safety, Simulation, Statistical distributions
Proceedings Papers

A Neutronics Feasibility Study of the TRIGA LEU Fuel in the 20MWt NIST Research Reactor

Kyle Anthony Britton, Zeyun Wu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A088, July 22–26, 2018
Paper No: ICONE26-82433
DOI: https://doi.org/10.1115/ICONE26-82433
View Paper titled, A Neutronics Feasibility Study of the TRIGA LEU Fuel in the 20MWt NIST Research Reactor
Click here to open pdf in another window PDF for A Neutronics Feasibility Study of the TRIGA LEU Fuel in the 20MWt NIST Research Reactor
Topics: Fuels, National Institute of Standards and Technology, Uranium, Density, Dimensions, Fuel rods, Performance characterization, Sustainability
Proceedings Papers

A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification

Wankui Yang, Baoxin Yuan, Songbao Zhang, Haibing Guo, Yaoguang Liu, Li Deng
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A032, July 22–26, 2018
Paper No: ICONE26-81709
DOI: https://doi.org/10.1115/ICONE26-81709
View Paper titled, A Neutron Transport Calculation Method for Deep Penetration and its Preliminary Verification
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Topics: Computational methods, Neutrons, Geometry, Modeling, Monte Carlo methods, China, Cross section (Physics), Finishes, Slabs, Tin
Proceedings Papers

Uranium Enrichment Measurement Using Enrichment-Meter Approach

K. Abd El Gawad, Yushou Song
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A039, July 22–26, 2018
Paper No: ICONE26-82101
DOI: https://doi.org/10.1115/ICONE26-82101
View Paper titled, Uranium Enrichment Measurement Using Enrichment-Meter Approach
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Topics: Uranium, Containers, Simulation, Accuracy and precision, Wall thickness, Calibration, Dimensions, Equilibrium (Physics), Gamma ray spectrometry, Germanium
Proceedings Papers

Mechanism of Flashing Phenomena Induced by Microwave Heating

Shunya Fujita, Yutaka Abe, Akiko Kaneko, Tomohisa Yuasa, Tomoomi Segawa, Yoshikazu Yamada, Yoshiyuki Kato, Katsunori Ishii
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A065, July 22–26, 2018
Paper No: ICONE26-81699
DOI: https://doi.org/10.1115/ICONE26-81699
View Paper titled, Mechanism of Flashing Phenomena Induced by Microwave Heating
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Topics: Flashing, Microwave heating, Vessels, Boiling, Potassium, Transients (Dynamics), Irradiation (Radiation exposure), Microwaves, Temperature, Water