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Proceedings Papers

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Doctor Enivweru, Qingyu Wang, Abiodun Ayodeji, John Njoroge
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A021, August 8–12, 2022
Paper No: ICONE29-90736
DOI: https://doi.org/10.1115/ICONE29-90736
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Topics: Corrosion, Fuels, Hydrogen embrittlement, Pressurized water reactors, Cladding systems (Building), Hydrogen, Temperature, Accidents, Boundary-value problems, Coolants
Proceedings Papers

Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building

Akemi Nishida, Byunghyun Choi, Tadahiko Shiomi, Manabu Kawata, Yinsheng Li
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, V001T02A009, August 4–6, 2021
Paper No: ICONE28-64300
DOI: https://doi.org/10.1115/ICONE28-64300
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Topics: Damage, Design, Earthquakes, Evaluation methods, Failure mechanisms, Hazards, Probabilistic risk assessment, Probability, Regulations, Safety
Proceedings Papers

Evaluation of Decay Dose Rates for European DEMO Vacuum Vessel Structure

Simona Breidokaitė, Andrius Tidikas, Gediminas Stankūnas
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A031, August 4–5, 2020
Paper No: ICONE2020-16465
DOI: https://doi.org/10.1115/ICONE2020-16465
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Topics: Vacuum, Vessels, Cooling, Shells, Water, Isotopes, Neutrons, Radioisotopes, Stainless steel, Design
Proceedings Papers

Low-Cycle Strength of Elements of Constructions

Alexander Zvorykin, Roman Popov, Mykola Bobyr, Igor Pioro
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A057, July 22–26, 2018
Paper No: ICONE26-81860
DOI: https://doi.org/10.1115/ICONE26-81860
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Topics: Cycles, Deformation, Stress, Low cycle fatigue, Kinematics, Structural elements (Construction), Yield point
Proceedings Papers

A Recommended Method for SC Wall Design-Evaluation Regarding the Elasto-Plastic Behavior Under Beyond Design Basis Seismic Loading

Ziduan Shang, Xiao Huang, Yugang Sun, Meng Chu
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A003, July 22–26, 2018
Paper No: ICONE26-81088
DOI: https://doi.org/10.1115/ICONE26-81088
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Topics: Design, Composite materials, Concretes, Steel, Constitutive equations, Shear (Mechanics), Construction, Nuclear power stations, Plates (structures), Stress
Proceedings Papers

Neutronic Methodological Benchmarks With Simplified Geometries for the Gas Cooled Reactor Group Constant Generating Tools

E. Temesvari, B. Batki, M. Gren
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A009, July 22–26, 2018
Paper No: ICONE26-81427
DOI: https://doi.org/10.1115/ICONE26-81427
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Topics: Approximation, Doppler effect, Gas cooled reactors, Geometry, Leakage, Manufacturing, Modeling, Optical mirrors, Physics, Safety
Proceedings Papers

Analysis on the Dynamic Buckling Behavior of the Spacer Grid Structure

Yan Guo, Chenglong Gu, Wei Tian, Weicai Li
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A048, July 22–26, 2018
Paper No: ICONE26-82298
DOI: https://doi.org/10.1115/ICONE26-82298
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Topics: Buckling, Design, Fuels, Manufacturing, Mechanical properties, Pressurized water reactors, Stiffness, Stress, Structural elements (Construction), Vibration
Proceedings Papers

Hydrodynamic Loads Calculation of Pressurizer Safety Valve Discharge Piping Using RELAP/SCDAPSIM

S. Jiang, Z. Fu, J. K. Hohorst
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A022, July 22–26, 2018
Paper No: ICONE26-82035
DOI: https://doi.org/10.1115/ICONE26-82035
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Topics: Pipes, Safety, Stress, Valves, Fluids, Hot water, Steam, Modeling, Piping design, Pressure
Proceedings Papers

Experimental Study on the Interaction of Molten Sn With Water

Longkun He, Pengfei Liu, Xisi Zhang, Wenjun Hu, Bo Kuang, Liangzhang Wei
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A038, July 22–26, 2018
Paper No: ICONE26-82204
DOI: https://doi.org/10.1115/ICONE26-82204
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Topics: Tin, Water, Explosions, Coolants, Water temperature, Pressure, Accidents, Containment, Fuels, Metals
Proceedings Papers

Verification of Probabilistic Fracture Mechanics Analysis Code PASCAL

Yinsheng Li, Genshichiro Katsumata, Koichi Masaki, Shotaro Hayashi, Yu Itabashi, Masaki Nagai, Masahide Suzuki, Yasuhiro Kanto
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A050, July 2–6, 2017
Paper No: ICONE25-66468
DOI: https://doi.org/10.1115/ICONE25-66468
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Topics: Fracture mechanics, Fracture (Process), Embrittlement, Irradiation (Radiation exposure), Light water reactors, Neutrons, Nuclear power, Nuclear power stations, Pressure, Reactor vessels
Proceedings Papers

Heat Transfer Simulation of the Fuel Transport Cask for Spherical Fuel Elements in Molten Salt Reactor

Yang Liu, Jun Wang
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A047, June 26–30, 2016
Paper No: ICONE24-60633
DOI: https://doi.org/10.1115/ICONE24-60633
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Topics: Fuels, Heat transfer, Molten salt reactors, Simulation, Accidents, Boiling water reactors, Design, Operating temperature, Pressurized water reactors, Radiation (Physics)
Proceedings Papers

Developing Structural Design Criteria for Fusion Reactor In-Vessel Components

M. Kalsey, M. Porton
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T14A008, July 7–11, 2014
Paper No: ICONE22-31216
DOI: https://doi.org/10.1115/ICONE22-31216
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Topics: Fusion reactors, Structural design, Vessels, Design, Conceptual design, Construction, Engineering design, Human factors, Power stations, Structural elements (Construction)
Proceedings Papers

Preliminary Development of System Analysis Code for Traveling-Wave Reactor

Chao Guo, Daogang Lu, Hao Huang
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A017, July 29–August 2, 2013
Paper No: ICONE21-15737
DOI: https://doi.org/10.1115/ICONE21-15737
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Topics: Systems analysis, Traveling waves, Fuels, Uranium, Light water reactors, Nuclear reactors, Safety, Centrifugal pumps, China, Design
Proceedings Papers

The Design of a Small Annular Linear Induction EM Pump for the Transportation of Liquid Sodium in the SFR

Hee Reyoung Kim
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A043, July 29–August 2, 2013
Paper No: ICONE21-16162
DOI: https://doi.org/10.1115/ICONE21-16162
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Topics: Design, Electromagnetic induction, Pumps, Sodium, Sodium fast reactors, Transportation systems, Pressure, High temperature, Circuits, Coolants
Proceedings Papers

Evaluation of Concrete Structures Using Nondestructive Techniques

Hemant S. Limaye
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 9-16, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54088
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54088
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Topics: Concretes, Building renovation, Construction, Nondestructive evaluation, Nuclear power stations, Structural elements (Construction)
Proceedings Papers

Nanostructural Characterization of Ni-Base Alloy/Low Alloy Steel Dissimilar Metal Weld (DMW) Interfaces

Kyoung Joon Choi, Jong Jin Kim, Ji Hyun Kim
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 551-558, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-55199
DOI: https://doi.org/10.1115/ICONE20-POWER2012-55199
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Topics: Alloy steel, Alloys, Metals, Nozzles, Filler metals, Light water reactors, Secondary ion mass spectrometry, Welded joints, Atoms, Boilers
Proceedings Papers

Hydrogen Ingress Into Zirconium Alloys as a Life-Limiting Factor — Methods of In-Line Monitoring, Prediction and Control

M. B. Elmoselhi, K. Tashiro, A. C. Wallace
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 301-307, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-54143
DOI: https://doi.org/10.1115/ICONE20-POWER2012-54143
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Topics: Hydrogen, Zirconium alloys, Alloys, Corrosion, Boiling water reactors, Cladding systems (Building), Coolants, Cracking (Materials), Diffusion (Physics), Fracture (Process)
Proceedings Papers

Evolution of Microstructure, Microtexture and Texture in Dilute Zirconium Based Structural Components of Pressurised Heavy Water Reactors

D. Srivastava, K. V. Mani Krishna, S. Neogy, G. K. Dey, I. Samajdar, S. Banerjee
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 401-409, July 12–16, 2009
Paper No: ICONE17-75274
DOI: https://doi.org/10.1115/ICONE17-75274
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Topics: Heavy water reactors, Structural elements (Construction), Texture (Materials), Zirconium, Alloys, Zirconium alloys, Phase transitions, Annealing, Cladding systems (Building), Corrosion
Proceedings Papers

COSI Test Case Simulation With CFX Code

Tony Glantz
Proc. ASME. ICONE17, Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control, 659-666, July 12–16, 2009
Paper No: ICONE17-75923
DOI: https://doi.org/10.1115/ICONE17-75923
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Topics: Simulation, Fluids, Computational fluid dynamics, Pressurized water reactors, Water, Condensation, Temperature, Thermal shock, Accidents, Coolants
Proceedings Papers

An Approach for Assessing Fuel Assembly’s Structural Integrity Under In-Core Operating Conditions Using Finite Element Method

Wei Zhao, Yuriy Aleshin
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 181-186, July 12–16, 2009
Paper No: ICONE17-75565
DOI: https://doi.org/10.1115/ICONE17-75565
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Topics: Finite element methods, Fuels, Stress, Design, Finite element analysis, Irradiation (Radiation exposure), Springs, Structural elements (Construction), Absorption, Creep