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Proceedings Papers

Simulation of Detection Efficiency of High Integrity Container Gamma Scanning Device for Nuclear Power Plant Based on CZT Detector

Wenzhang Xie, Jia Huang, Chenyu Shan, Qingxin Lei, Kang Chang, Hao Zhou, Feng Liu, Peng Lin, Xiajie Liu, Li Li
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A012, August 8–12, 2022
Paper No: ICONE29-91233
DOI: https://doi.org/10.1115/ICONE29-91233
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Topics: Containers, Nuclear power stations, Sensors, Simulation, Density, Radioactive wastes, Chemical stability, Engineering standards, Evaporation, Filtration
Proceedings Papers

Study on Preparation and Radioactive Methyl-Iodine Adsorption Performance of TEDA Ionic Liquids

Xin Li, Yongguo Li, Jie Yu, Xin Chen, Jianrong Hou, Jian Li, Dangui Qiu, Xu Shi
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A006, August 8–12, 2022
Paper No: ICONE29-90275
DOI: https://doi.org/10.1115/ICONE29-90275
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Topics: Activated carbon, Fibers, Infrared spectra, Nuclear power stations, Solid wastes, Temperature, Thermal stability, Thermogravimetry
Proceedings Papers

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Kaiyuan Wang, Xiaohan Liu, Xin Jin
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A021, August 8–12, 2022
Paper No: ICONE29-89917
DOI: https://doi.org/10.1115/ICONE29-89917
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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission
Proceedings Papers

Investigation on Thermal Stability of Sintered Magnesia in Sodium for Core Catcher Application in SFRs

Prabhat Kumar Shukla, E. Hemanth Rao, Muthuganesh M., E. Vetrivendan, S. R. Polaki, Sanjay Kumar Das, S. Ningshen, Pramod Kumar Chaurasia, D. Ponraju, S. Athmalingam, B. Venkatraman
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, V003T12A034, August 4–6, 2021
Paper No: ICONE28-65785
DOI: https://doi.org/10.1115/ICONE28-65785
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Topics: Accidents, Fast neutron reactors, Sodium, Sodium fast reactors, Thermal stability
Proceedings Papers

Primary Study on Carbon Dioxide Power Cycle of HTGR

Chengjie Duan, Xiaoyong Yang, Jie Wang, Suyuan Yu
Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 667-673, May 11–15, 2008
Paper No: ICONE16-48219
DOI: https://doi.org/10.1115/ICONE16-48219
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Topics: Carbon dioxide, Thermodynamic power cycles, Very high temperature reactors, Cycles, Helium, Pressure, Steam, Fluids, Brayton cycle, Density