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Proceedings Papers

Further Study on Real-Time Positioning of Fuel Failures Method in HFETR

Shouhua Sun, Jian Li
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A009, August 4–6, 2021
Paper No: ICONE28-64210
DOI: https://doi.org/10.1115/ICONE28-64210
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Topics: Failure, Fuels, Radioisotopes, Chain, Cladding systems (Building), Coolants, Corrosion, Damage, Fracture (Materials), Manufacturing
Proceedings Papers

Cause Analysis and Influence Evaluation of Cracks in Thick Slab Construction

Yi Guixiang, Li Liang
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, V001T02A021, August 4–6, 2021
Paper No: ICONE28-64548
DOI: https://doi.org/10.1115/ICONE28-64548
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Topics: Construction, Fracture (Materials), Slabs
Proceedings Papers

Development of Digital Twins of PWR Steam Generators: Description of Two Maintenance-Oriented Use Cases

Enrico Deri, Christophe Varé, Matthieu Wintergerst
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, V001T01A002, August 4–6, 2021
Paper No: ICONE28-63246
DOI: https://doi.org/10.1115/ICONE28-63246
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Topics: Boilers, Maintenance, Pressurized water reactors, Computation, Design, Emergency preparedness, Engineering disciplines, Fracture (Materials), Inspection, Instrumentation
Proceedings Papers

Effects of Pre-Crack Depth and Hydrogen Absorption on the Failure Strain of Zircaloy-4 Cladding Tubes Under Biaxial Strain Conditions

Feng Li, Takeshi Mihara, Yutaka Udagawa, Masaki Amaya
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A052, August 4–5, 2020
Paper No: ICONE2020-16738
DOI: https://doi.org/10.1115/ICONE2020-16738
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Topics: Absorption, Cladding systems (Building), Failure, Fracture (Materials), Hydrogen, Heat treating (Metalworking), Accidents, Fuels, Manufacturing, Metals
Proceedings Papers

IHSI Effectiveness for Crack Propagation Observed at Hamaoka PLR Piping

Hideki Yuya, Kouji Yamada, Takao Sasayama
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, V001T06A004, August 4–5, 2020
Paper No: ICONE2020-16090
DOI: https://doi.org/10.1115/ICONE2020-16090
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Topics: Crack propagation, Electromagnetic induction, Fracture (Materials), Heat, Pipes, Stress, Ultrasonic testing, Cutting, Plant construction
Proceedings Papers

Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings

Nak-Kyun Cho, Pavitra Bansal, Antony M. Hurst
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, V001T06A015, August 4–5, 2020
Paper No: ICONE2020-16426
DOI: https://doi.org/10.1115/ICONE2020-16426
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Topics: Boilers, Pressure, Transients (Dynamics), Valves, Pipes, Temperature, Collapse, Engineers, Fatigue, Flow (Dynamics)
Proceedings Papers

Probability of Rupture for WWER-1000 Main Piping

Yaroslav Dubyk, Maksym Zarazovskii, Sergii Ageiev, Vladislav Filonov
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A014, August 4–5, 2020
Paper No: ICONE2020-16897
DOI: https://doi.org/10.1115/ICONE2020-16897
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Topics: Leakage, Pipes, Probability, Rupture, Stress, Fracture (Materials), Accounting, Flow (Dynamics), Fracture toughness, Nuclear power stations
Proceedings Papers

LBB Analysis on Nuclear-Class Pipes of Floating Nuclear Power Stations

Fan Bai, Yong Liu, Xingsheng Lao, Qi Xiao, Zhenxing Zhao, Jun Wu, Can Ma, Wang Wei
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A029, July 22–26, 2018
Paper No: ICONE26-82180
DOI: https://doi.org/10.1115/ICONE26-82180
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Topics: Nuclear power stations, Pipes, Fracture (Materials), Leakage, Design, Drilling, Fatigue, Finite element methods, Fracture mechanics, Leak-before-break
Proceedings Papers

A Structural Integrity Assessment of a Nuclear Boiler Superheater Bifurcation at High Temperature

Brahim Nadri, Robert X. Wang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A005, July 22–26, 2018
Paper No: ICONE26-81167
DOI: https://doi.org/10.1115/ICONE26-81167
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Topics: Bifurcation, Boilers, High temperature, Superheaters, Creep, Metals, Fatigue, Fracture (Materials), Safety, Boiler tubes
Proceedings Papers

Development of a Crack Opening Displacement Assessment Procedure Considering Change of Compliance at a Crack Part in Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Seiji Yanagihara, Ryosuke Suzuki, Masaaki Matsubara
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A035, July 22–26, 2018
Paper No: ICONE26-82619
DOI: https://doi.org/10.1115/ICONE26-82619
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Topics: Displacement, Fracture (Materials), Pipes, Steel, Thin wall structures, Leakage, Sodium fast reactors, Sodium, Work hardening, Coolants
Proceedings Papers

Development of Laser Cleaning for Metallic Equipment

L. Carvalho, W. Pacquentin, M. Tabarant, J. Lambert, A. Semerok, H. Maskrot
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A015, July 22–26, 2018
Paper No: ICONE26-81853
DOI: https://doi.org/10.1115/ICONE26-81853
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Topics: Lasers, Contamination, Decontamination, Geometry, Stainless steel, Cobalt, Coolants, Diffusion (Physics), Emissions, Europium
Proceedings Papers

Numerical Impact Simulation of Aircraft Into Reinforced Concrete Walls With Different Thickness

Kazuma Hirosaka, Hidekazu Takazawa, Katsumasa Miyazaki, Norihide Tohyama, Hiroyuki Nouji, Naomi Matsumoto
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A047, July 22–26, 2018
Paper No: ICONE26-82616
DOI: https://doi.org/10.1115/ICONE26-82616
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Topics: Aircraft, Reinforced concrete, Simulation, Phantoms, Concrete walls, Simulation models, Computer simulation, Damage, Impact testing, Kinematics
Proceedings Papers

New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes

Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A002, July 22–26, 2018
Paper No: ICONE26-81096
DOI: https://doi.org/10.1115/ICONE26-81096
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Topics: Design, Fracture (Materials), Fracture (Process), Boilers, Brittle fracture, Brittleness, Failure, In-service inspection, Leak-before-break, Manufacturing
Proceedings Papers

Study on Hydrogen Migration in Small Water Leak of Sodium-Cooled Fast Reactor

Xinjie Deng, Xuewu Cao
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A021, July 22–26, 2018
Paper No: ICONE26-81314
DOI: https://doi.org/10.1115/ICONE26-81314
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Topics: Hydrogen, Sodium fast reactors, Water leakage, Sodium, Circuits, Water, Leakage, Boilers, Fracture (Materials), Heat
Proceedings Papers

A Theoretical Model of the Stress Intensity Factor Threshold of DHC for Fuel Cladding Tube

Liang Chen, Lili Liu, Xiaoming Song, Hua Pang
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A031, July 22–26, 2018
Paper No: ICONE26-81665
DOI: https://doi.org/10.1115/ICONE26-81665
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Topics: Cladding systems (Building), Fuels, Stress, Temperature, Fracture (Materials), Temperature gradient, Cracking (Materials), Diffusion (Physics), Fracture (Process), Hydrogen
Proceedings Papers

Thermal Hydraulic Analysis of Pressurized Thermal Shock for Loviisa NPP Using Apros Simulation Code

Gintaras Žemulis, Pasi Junninen, Petri Kytömäki
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A051, July 22–26, 2018
Paper No: ICONE26-81558
DOI: https://doi.org/10.1115/ICONE26-81558
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Topics: Nuclear power stations, Simulation, Thermal shock, Safety, Emergencies, Reactor vessels, Embrittlement, Heat, Boundary-value problems, Cooling
Proceedings Papers

Effect of Subcooling and Nozzle Diameter on Heat Transfer Characteristics of Downward Facing Hot Surfaces Using Mist Jet

Avadhesh Kumar Sharma, Monika Meena, Anirudh Soni, Santosh K. Sahu
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A040, July 22–26, 2018
Paper No: ICONE26-82211
DOI: https://doi.org/10.1115/ICONE26-82211
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Topics: Heat transfer, Nozzles, Subcooling, Heat flux, Cooling, Impingement cooling, Temperature, Compressed air, Drops, Ductility
Proceedings Papers

Sensitivity Analysis of the SBLOCA Induced Severe Accident for a Natural Circulation Small Modular Reactors

Longze Li, Jue Wang, Yapei Zhang, G. H. Su
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A047, July 22–26, 2018
Paper No: ICONE26-82267
DOI: https://doi.org/10.1115/ICONE26-82267
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Topics: Accidents, Sensitivity analysis, Small modular reactors, Containment, Fracture (Materials), Pressure, Heat sinks, Accident management, Boilers, Containment vessels
Proceedings Papers

Research on Simplified Method of Transients Combining and Loading in Fatigue Crack Growth Analysis of Carbon Steel Nuclear Piping

Zhenshun Liu, Hongdong Zhen
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A019, July 22–26, 2018
Paper No: ICONE26-81640
DOI: https://doi.org/10.1115/ICONE26-81640
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Topics: Carbon steel, Fatigue cracks, Pipes, Transients (Dynamics), Fracture (Materials), Stress, ASME Standards, Fatigue
Proceedings Papers

The Compatibility of Nuclear Graphite With Molten Salt in the Molten Salt Reactor

Zhoutong He, Hui Tang, Can Zhang, Yantao Gao, Huihao Xia, Xingtai Zhou
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A026, July 22–26, 2018
Paper No: ICONE26-82065
DOI: https://doi.org/10.1115/ICONE26-82065
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Topics: Graphite, Molten salt reactors, Temperature, Strength (Materials), Thermal expansion, Coolants, Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure), Pressure