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Proceedings Papers

Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel

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Duan Qianni, Li Wei, Wu Junmei
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
https://doi.org/10.1115/ICONE31-135085
View Paper titled, Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel
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Topics: High cycle fatigue, Nuclear fuels, Neutrons, Physics, Power density, Fuels, Geometry, Innovation, Thermal hydraulics, Uranium
Proceedings Papers

Analysis of Shielding Structures of Radioactive Material Transport Package Based on Isotope Γ Radiation Properties in Radioactive Materials

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Zhi-peng Wang, Chang-wu Wang, Qian Sun, Yu-hang Zhang
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
https://doi.org/10.1115/ICONE31-136353
View Paper titled, Analysis of Shielding Structures of Radioactive Material Transport Package Based on Isotope Γ Radiation Properties in Radioactive Materials
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Topics: Isotopes, Radiation (Physics), Radioactive substances, Spectra (Spectroscopy), Transport packages, Uranium
Proceedings Papers

The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme

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Songyang Liu, Xuelin Li, Yong Luo, Wei Liu, Qin Zhou, Cheng Gu, Tian Zhang
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
https://doi.org/10.1115/ICONE31-133310
View Paper titled, The Steady States and DLOFC Accident Analysis of HTR-PM in the OTTO Operation Scheme
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Topics: Accidents, Steady state, Fuels, Temperature, China, Equilibrium (Physics), Graphite, Construction, Coolants, Design
Proceedings Papers

Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core

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Guihua Lai, Tian Wang, Ding She, Hong Wang
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
https://doi.org/10.1115/ICONE31-135206
View Paper titled, Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core
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Topics: Conceptual design, Fast neutron reactors, Small modular reactors, Supercritical carbon dioxide, Safety, Temperature, Design, Fuel rods, Heat, Particulate matter
Proceedings Papers

Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor

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Takeshi Koike, Koji Asano, Mizuki Yamada, Satoru Kamohara, Tadakatsu Yodo, Nozomu Murakami
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
https://doi.org/10.1115/ICONE31-135017
View Paper titled, Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor
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Topics: Design, Heat transfer, Neutrons, Safety, Reliability, Carbon, Fuels, Graphite, Heat, Light water reactors
Proceedings Papers

The Neutronics Analysis of Heat Pipe Cooled Traveling Wave Reactor Designs With High-Assay Low-Enrichment Uranium and Natural Uranium

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Po Hu, Kunfeng Ma
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
https://doi.org/10.1115/ICONE31-136201
View Paper titled, The Neutronics Analysis of Heat Pipe Cooled Traveling Wave Reactor Designs With High-Assay Low-Enrichment Uranium and Natural Uranium
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Topics: Heat pipes, Traveling waves, Uranium
Proceedings Papers

AWCC Simulations Based on Monte Carlo Code RMC

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Yuanhao Gou, Zhaoyuan Liu, Conglong Jia, Dacai Zhang, Hao Luo, Kan Wang
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
https://doi.org/10.1115/ICONE31-132066
View Paper titled, AWCC Simulations Based on Monte Carlo Code RMC
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Topics: Design, Emissions, Engineering simulation, Gates (Closures), Instrumentation, Neutrons, Nuclear fission, Simulation, Uranium
Proceedings Papers

Influence of Thorium Utilization on the Safety of a Small Modular Molten Salt Reactor

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Jianhui 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
https://doi.org/10.1115/ICONE31-134819
View Paper titled, Influence of Thorium Utilization on the Safety of a Small Modular Molten Salt Reactor
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Topics: Molten salt reactors, Nuclear fuel cycle, Safety, Temperature, Transients (Dynamics), Uranium
Proceedings Papers

Simulation Calculation of the Utilization Rate of Uranium Resources on the ADANES Fuel Cycle

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Xuesong Yan, Yucui Gao, Yaling Zhang, Lei Yang
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
https://doi.org/10.1115/ICONE31-130623
View Paper titled, Simulation Calculation of the Utilization Rate of Uranium Resources on the ADANES Fuel Cycle
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Topics: Fuels, Nuclear fuel cycle, Nuclear power, Simulation, Uranium
Proceedings Papers

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

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Guang-Yu Shi, Shi-Wei Jing
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A015, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89597
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

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Sina Li, Binhuo Yan, Guojun Tang, Donghong Peng, Hongzhi Lu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A017, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89659
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

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92285
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
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91817
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
Open the PDF for Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor in another window
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91804
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

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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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90894
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91465
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
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-66589
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65765
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64357
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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16143
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