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Proceedings Papers
Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel
Available to Purchase
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A035, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135085
Proceedings Papers
Analysis of Shielding Structures of Radioactive Material Transport Package Based on Isotope Γ Radiation Properties in Radioactive Materials
Available to Purchase
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A062, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136353
Proceedings Papers
The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme
Available to Purchase
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133310
Proceedings Papers
Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core
Available to Purchase
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135206
Proceedings Papers
Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor
Available to Purchase
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135017
Proceedings Papers
The Neutronics Analysis of Heat Pipe Cooled Traveling Wave Reactor Designs With High-Assay Low-Enrichment Uranium and Natural Uranium
Available to Purchase
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A067, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136201
Proceedings Papers
AWCC Simulations Based on Monte Carlo Code RMC
Available to Purchase
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132066
Proceedings Papers
Influence of Thorium Utilization on the Safety of a Small Modular Molten Salt Reactor
Available to PurchaseJianhui Wu, Chunyan Zou, Chenggang Yu, Hongkai Zhao, Yong Cui, Haotian Bao, Xiangzhou Cai, Jingen Chen
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A030, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134819
Proceedings Papers
Simulation Calculation of the Utilization Rate of Uranium Resources on the ADANES Fuel Cycle
Available to Purchase
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A001, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130623
Proceedings Papers
Active Interrogation of Highly Enriched Uranium in the Suitcase by Using NG-9 Neutron Generator
Available to Purchase
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A015, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89597
Proceedings Papers
Preliminary Design and Neutronics Analysis for a Medium Temperature Heat Pipe Cooled Reactor
Available to Purchase
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A017, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89659
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
Available to Purchase
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A053, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92285
Proceedings Papers
Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor
Available to Purchase
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A041, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91817
Proceedings Papers
Numerical Simulation Analysis of Silicon Carbide Whiskers Doped Uranium Dioxide Composite Fuel for High Thermal Conductivity
Available to Purchase
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A040, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91804
Proceedings Papers
Comparison of the Powderization Effect of Non-Equilibrium Plasma Oxidation and Thermochemical Oxidation Powders of Uranium Dioxide Solids for Actinide Analysis
Available to Purchase
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90894
Proceedings Papers
The Location of Spent Fuel Pins in Heavy Water Research Reactor in the Spent Fuel Pool
Available to Purchase
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91465
Proceedings Papers
Levelized Cost of Electricity Evaluation Methodology Applied to High-Burnup 18 and 24-Month Fuel Cycles
Available to Purchase
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A019, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66589
Proceedings Papers
A Sodium-Cooled Thermal-Spectrum Fission Battery
Available to Purchase
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65765
Proceedings Papers
Summary of the Practice of Clearance of Uranium-Containing Calcium Fluoride Slags in China’s Nuclear Facilities
Available to Purchase
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64357
Proceedings Papers
Uranium Radioactivity Measurement for Low-Level Wastewater Based on Ultra-Low Level Liquid Scintillation Analyzer
Available to Purchase
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16143
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