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Proceedings Papers

Effect of Hydration Time on the Hydro-Mechanical Behavior of Compacted GMZ Bentonite With an Artificial Annular Gap

Hewen Luo, Weimin Ye, Qiong Wang, Libo Xu

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A021, August 8–12, 2022

Paper No: ICONE29-92182

DOI: https://doi.org/10.1115/ICONE29-92182

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Topics: Compression, Conceptual design, Density, Hydraulic conductivity, Polishing equipment, Pressure, Radioactive wastes, Rocks, Water

Proceedings Papers

Study on the Application of Electromagnetic Stepping CRDM at Tilted Environment

Zhaohui Lu, Zewen Li, Jianming Zhou, Qingsong Liu

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A005, August 8–12, 2022

Paper No: ICONE29-90150

DOI: https://doi.org/10.1115/ICONE29-90150

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Topics: Design, Engineering prototypes, Failure, Kinematics, Polishing equipment, Pressurized water reactors, Stress, Structural design, Surface finishing, Wear

Proceedings Papers

Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors

Mohammad Alrwashdeh, Saeed A. Alameri

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, V001T05A014, August 4–5, 2020

Paper No: ICONE2020-16838

DOI: https://doi.org/10.1115/ICONE2020-16838

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Topics: Fuels, Particulate matter, Very high temperature reactors, Coating processes, Coatings, Cycles, Graphite, High temperature, Monte Carlo methods, Nuclear fuel cycle

Proceedings Papers

Ultrasonic Velocities Measurement in Compacted Bentonite-Sand Mixtures for Saturation Level Evaluation

Shun Kimura, Hideharu Takahashi, Ari Hamdani, Masanori Aritomi, Susumu Ozaki, Hiroshige Kikura

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A025, July 22–26, 2018

Paper No: ICONE26-82617

DOI: https://doi.org/10.1115/ICONE26-82617

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Topics: Bulk modulus, Elasticity, Groundwater, Longitudinal waves, Monitoring systems, Polishing equipment, Radioactive waste disposal, Safety, Sands, Speed of sound

Proceedings Papers

Research on Auxiliary Bearing Structure With Buffer Shim Based on LS-DYNA for Helium Circulator of HTR-10

Guojun Yang, Zhe Sun, Xingnan Liu, Zhengang Shi

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A013, July 22–26, 2018

Paper No: ICONE26-81304

DOI: https://doi.org/10.1115/ICONE26-81304

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Topics: Bearings, Helium, Polishing equipment, Rotors, Stress, Damage, Stress concentration, Computer software, Deformation, Finite element methods

Proceedings Papers

Numerical and Experimental Analysis of the Control Rod Hydraulic Deceleration Device for the Control Rod Hydraulic Drive System

Qin Benke, Li Leishi, Bo Hanliang

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A049, July 2–6, 2017

Paper No: ICONE25-66463

DOI: https://doi.org/10.1115/ICONE25-66463

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Topics: Experimental analysis, Hydraulic drive systems, Cylinders, Temperature, Flow (Dynamics), Scram, Blades, Design, Dynamics (Mechanics), Fuels

Proceedings Papers

Research of the Rod Drop Time Based on the Control Rod System of TMSR-SF1

Zuokang Lin, Lin Zhu, Chunfeng Zhao, Yun Cao, Xiao Wang

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A073, July 2–6, 2017

Paper No: ICONE25-66921

DOI: https://doi.org/10.1115/ICONE25-66921

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Topics: Accidents, Control systems, Density, Disks, Earthquakes, Errors, Experimental methods, Molten salt reactors, Polishing equipment, Rods

Proceedings Papers

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 2 — Design Study of Fuel and Reactor Core

Minoru Goto, Shohei Ueta, Jun Aihara, Yoshitomo Inaba, Yuji Fukaya, Yukio Tachibana, Koji Okamoto

Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A031, July 2–6, 2017

Paper No: ICONE25-67110

DOI: https://doi.org/10.1115/ICONE25-67110

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Topics: Design, Fuels, Safety, Security, Very high temperature reactors, Pressure, Oxygen, Coating processes, Coatings, Failure

Proceedings Papers

CFD Analysis Technique Development for Wire Contact Effect of Fuel Rods Within Next Generation FBR in Japan

Hironori Nakamura, Kazuhiro Oyama, Satoshi Hayakawa, Tomoaki Ogata, Seiichiro Maeda, Takayuki Ozawa

Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A013, July 2–6, 2017

Paper No: ICONE25-66307

DOI: https://doi.org/10.1115/ICONE25-66307

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Topics: Computational fluid dynamics, Fuel rods, Wire, Fuels, Boundary-value problems, Cladding systems (Building), Geometry, Simulation, Sodium fast reactors, Temperature

Proceedings Papers

Effects of Temperature on Deposition Rate of Supersaturated Silicic Acid on Ca-Type Bentonite

Tsuyoshi Sasagawa, Taiji Chida, Yuichi Niibori

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A032, June 26–30, 2016

Paper No: ICONE24-60468

DOI: https://doi.org/10.1115/ICONE24-60468

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Topics: Cements (Building materials), Construction, Flow (Dynamics), Groundwater, Minerals, Polishing equipment, Radioactive wastes, Radioisotopes, Temperature, Temperature effects

Proceedings Papers

Fundamental Study on Application of Ultrasonic Velocimetry to Molten Glass

Tomonori Ihara, Nobuyoshi Tsuzuki, Hiroshige Kikura

Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A016, July 7–11, 2014

Paper No: ICONE22-30695

DOI: https://doi.org/10.1115/ICONE22-30695

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Topics: Glass, Polishing equipment, Ultrasound, Echoes, Temperature, Absorption, Acoustics, Borosilicate glasses, Ceramics, Corrosion resistance

Proceedings Papers

Experimental Study of Feed Water Level Decreasing Effect on VVER Steam Generator Model Operation in Condensation Mode

A. V. Morozov, O. V. Remizov, A. S. Soshkina

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A043, July 29–August 2, 2013

Paper No: ICONE21-16470

DOI: https://doi.org/10.1115/ICONE21-16470

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Topics: Boilers, Condensation, Feedwater, Accidents, Circuits, Steam, Test facilities, Cooling, Design, Heat

Proceedings Papers

Development of High Temperature Gas-Cooled Reactor Fuel for Extended Burnup

Shohei Ueta, Jun Aihara, Masaki Honda, Noboru Furihata, Kazuhiro Sawa

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 11-12, May 17–21, 2010

Paper No: ICONE18-29206

DOI: https://doi.org/10.1115/ICONE18-29206

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Topics: Fuels, Very high temperature reactors, Carbon, Coating processes, Coatings, Particulate matter, Nuclear fission, High temperature, Nuclear power, Polishing equipment

Proceedings Papers

Thermal Conduction Experiments on Compacted GMZ Bentonite Blocks as the Potential Buffer Materials for HLW Disposal Purpose

Guang-yuan Ren, Xiao-dong Liu, Qing-chun Chen, Guo-ping Zhu, Quan-shui Chen

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 413-419, May 17–21, 2010

Paper No: ICONE18-29287

DOI: https://doi.org/10.1115/ICONE18-29287

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Topics: Heat conduction, Polishing equipment, Temperature, Cylinders, Heat, Temperature gradient, Compacting, Density, Design, Heating

Proceedings Papers

Experimental Comparisons of 3D Reconstructed Pin-Power Distributions in Full-Scale BWR Fuel Assemblies

Flavio D. Giust, Peter Grimm, Rakesh Chawla

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 2, 227-236, May 17–21, 2010

Paper No: ICONE18-29691

DOI: https://doi.org/10.1115/ICONE18-29691

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Topics: Boiling water reactors, Fuels, Blades, Gadolinium, Diffusion (Physics), Nuclear fission, Nuclear power stations, Polishing equipment, Rods, Temperature

Proceedings Papers

Investigation of Chemical Effects on Emergency Core Cooling Filtration Head Loss After Loss of Coolant Accident

Jong Woon Park, Byung Gi Park, Chang Hyun Kim

Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 511-518, July 12–16, 2009

Paper No: ICONE17-75398

DOI: https://doi.org/10.1115/ICONE17-75398

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Topics: Accidents, Coolants, Cooling, Emergencies, Filtration, Aluminum, Filters, Sprays, Sodium, Building materials

Proceedings Papers

Experimental Study on the Effects of Fault Movement on the Engineered Barrier System

Morimasa Naito, Yuya Saito, Kenji Tanai, Mikazu Yui

Proc. ASME. ICONE16, Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 153-158, May 11–15, 2008

Paper No: ICONE16-48833

DOI: https://doi.org/10.1115/ICONE16-48833

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Topics: Metals, Numerical analysis, Plasticity, Polishing equipment, Simulation, Testing equipment

Proceedings Papers

Detailed Multi Canister Release Model of Radionuclides in High Level Radioactive Waste Repository Using Wavelet Galerkin Method

Hesham R. Nasif, Atsushi Neyama

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 485-490, April 14–18, 2002

Paper No: ICONE10-22720

DOI: https://doi.org/10.1115/ICONE10-22720

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Topics: Galerkin method, Radioactive wastes, Radioisotopes, Wavelets, Polishing equipment, Rocks, Diffusion (Physics), Glass, Hydraulic conductivity, Nuclides

Proceedings Papers

Integrated Multi Path Model to Calculate Radionuclide Release From a Repository Using Wavelet Galerkin Method

Hesham R. Nasif, Atsushi Neyama

Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 491-500, April 14–18, 2002

Paper No: ICONE10-22721

DOI: https://doi.org/10.1115/ICONE10-22721

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Topics: Galerkin method, Radioisotopes, Wavelets, Diffusion (Physics), Rocks, Water, Algorithms, Bearings, Failure, Fracture (Materials)

Proceedings Papers

Safety Design and Mock-Up Tests on the Combustion of Hydrogen-Air Mixture in the Vertical CNS Channel of the CARR-CNS

Qingfeng Yu, Quanke Feng

Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 393-398, July 17–20, 2006

Paper No: ICONE14-89815

DOI: https://doi.org/10.1115/ICONE14-89815

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Topics: Combustion, Design, Hydrogen, Safety, Helium, Condensers (steam plant), Pressure, Accidents, Cooling, Aluminum alloys

NARROW

Effect of Hydration Time on the Hydro-Mechanical Behavior of Compacted GMZ Bentonite With an Artificial Annular Gap

Study on the Application of Electromagnetic Stepping CRDM at Tilted Environment

Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors

Ultrasonic Velocities Measurement in Compacted Bentonite-Sand Mixtures for Saturation Level Evaluation

Research on Auxiliary Bearing Structure With Buffer Shim Based on LS-DYNA for Helium Circulator of HTR-10

Numerical and Experimental Analysis of the Control Rod Hydraulic Deceleration Device for the Control Rod Hydraulic Drive System

Research of the Rod Drop Time Based on the Control Rod System of TMSR-SF1

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 2 — Design Study of Fuel and Reactor Core

CFD Analysis Technique Development for Wire Contact Effect of Fuel Rods Within Next Generation FBR in Japan

Effects of Temperature on Deposition Rate of Supersaturated Silicic Acid on Ca-Type Bentonite

Fundamental Study on Application of Ultrasonic Velocimetry to Molten Glass

Experimental Study of Feed Water Level Decreasing Effect on VVER Steam Generator Model Operation in Condensation Mode

Development of High Temperature Gas-Cooled Reactor Fuel for Extended Burnup

Thermal Conduction Experiments on Compacted GMZ Bentonite Blocks as the Potential Buffer Materials for HLW Disposal Purpose

Experimental Comparisons of 3D Reconstructed Pin-Power Distributions in Full-Scale BWR Fuel Assemblies

Investigation of Chemical Effects on Emergency Core Cooling Filtration Head Loss After Loss of Coolant Accident

Experimental Study on the Effects of Fault Movement on the Engineered Barrier System

Detailed Multi Canister Release Model of Radionuclides in High Level Radioactive Waste Repository Using Wavelet Galerkin Method

Integrated Multi Path Model to Calculate Radionuclide Release From a Repository Using Wavelet Galerkin Method

Safety Design and Mock-Up Tests on the Combustion of Hydrogen-Air Mixture in the Vertical CNS Channel of the CARR-CNS

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