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Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A046, July 2–6, 2017

Paper No: ICONE25-67860

DOI: https://doi.org/10.1115/ICONE25-67860

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Topics: Condensed matter, Nuclear power stations, Pipelines, Root cause analysis, Rupture, Failure mechanisms, Pressurized water reactors, Circuits, Corrective actions, Corrosion

Proceedings Papers

Preliminary Experimental Study on Erosion-Corrosion Behavior of Second Loop Pipeline in Nuclear Power Plant With Vapor Liquid Two Phase Flow

Pengfei Liu, Xian Zhang, Nan Zhao, Junliang Liu, Bo Kuang

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A113, July 2–6, 2017

Paper No: ICONE25-67762

DOI: https://doi.org/10.1115/ICONE25-67762

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Topics: Corrosion, Erosion, Nuclear power stations, Pipelines, Two-phase flow, Vapors, Flow (Dynamics), Pipes, Pressure, Pressure drop

Proceedings Papers

An Experimental Investigation on Drainage Performance of a Drain Device in a Steam Generator of PWR

Shengjie Gong, Yong Mei, Hanyang Gu, Binbin Ying, Yinxi Song

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A030, June 26–30, 2016

Paper No: ICONE24-60495

DOI: https://doi.org/10.1115/ICONE24-60495

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Topics: Boilers, Drainage, Pressurized water reactors, Pipes, Flow (Dynamics), Water, Matlab, Pressure, Steam, Temperature

Proceedings Papers

Numerical Investigation on Critical Submerged Depth During Draining From Cylindrical Tanks

Liu Shi-wen, Zhou Jie, Huang Wei, Cheng Xiang

Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A015, June 26–30, 2016

Paper No: ICONE24-60376

DOI: https://doi.org/10.1115/ICONE24-60376

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Topics: Drainage, Vortices, Computational fluid dynamics, Computer simulation, Damage, Design, Flow (Dynamics), Fluids, Nuclear engineering, Storage tanks

Proceedings Papers

Experimental Study on Model Development for Liquid Accumulation in Steam Generator U-Tube (First Report) Condensing Counter-Current Flow in Single Vertical Pipe

Tatsuya Yamaji, Kohei Yamazaki, Yasuo Koizumi, Hiroyasu Ohtake, Koji Hasegawa, Shota Araki, Akira Ohnuki, Hiroaki Nishi

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A043, July 7–11, 2014

Paper No: ICONE22-30568

DOI: https://doi.org/10.1115/ICONE22-30568

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Topics: Boilers, Flow (Dynamics), Model development, Pipes, Water, Steam, Accidents, Coolants, Drainage, Film flow

Proceedings Papers

Flow Instability Inside Heat Transfer Tubes of Moisture Separator Reheater

Jun Manabe

Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A038, July 7–11, 2014

Paper No: ICONE22-30297

DOI: https://doi.org/10.1115/ICONE22-30297

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Topics: Flow instability, Heat transfer, Turbines, Water, Condensation, Design, Drainage, Dynamics (Mechanics), Engineering systems and industry applications, Exhaust systems

Proceedings Papers

Study on Operating Criteria of the Supersonic Steam Injector

Kyosuke Satoh, Yutaka Abe, Akiko Kaneko

Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A021, July 29–August 2, 2013

Paper No: ICONE21-15962

DOI: https://doi.org/10.1115/ICONE21-15962

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Topics: Ejectors, Pressure, Water, Diffusers, Flow (Dynamics), Nozzles, Steam, Two-phase flow, Accidents, Condensation

Proceedings Papers

Study on Controlling Condensation Heat Transfer by Using Functionalized Heat Transfer Surface

Syota Yoshizawa, Sho Ikeda, Yasuo Koizumi

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A076, July 29–August 2, 2013

Paper No: ICONE21-16160

DOI: https://doi.org/10.1115/ICONE21-16160

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Topics: Condensation, Heat transfer, Gold plating, Copper, Steam, Condensed matter, Drainage, Shapes

Proceedings Papers

Scaling Analysis of the Pressurizer Surge Line in Nuclear Plant Integral Test Facilities

Cheng-Cheng Deng, Hua-Jian Chang, Ben-Ke Qin, Han Wang, Lian Chen

Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 197-204, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54304

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54304

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Topics: Nuclear power stations, Surges, Test facilities, Drainage, Accidents, China, Coolants, Cooling, Flow (Dynamics), Two-phase flow

Proceedings Papers

Slug Flow Main Parameters in a Combined Inclined Up and Down Two-Phase Flow

Florencio Sanchez-Silva, Ignacio Carvajal-Mariscal, Miguel Toledo-Velázquez, Georgiy Polupan

Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 525-532, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54635

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54635

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Topics: Slug flows, Two-phase flow, Flow (Dynamics), Porosity, Data acquisition systems, Drainage, Geometry, Pipes, Probes, Stratified flow

Proceedings Papers

Experiments and Simulations on the Steady-State and Transient Behavior of Gas/Liquid Interfaces in Impulse Pipes for Hydrostatic Level Measurements

Stephan Schulz, Rainer Hampel

Proc. ASME. ICONE20-POWER2012, Volume 5: Fusion Engineering; Student Paper Competition; Design Basis and Beyond Design Basis Events; Simple and Combined Cycles, 301-308, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54592

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54592

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Topics: Engineering simulation, Hydrostatics, Impulse (Physics), Pipes, Simulation, Steady state, Transients (Dynamics), Boiling water reactors, Flow (Dynamics), Fluctuations (Physics)

Proceedings Papers

Underwater Laser Beam Welding for Nuclear Reactors

Masaki Yoda, Masataka Tamura, Takeshi Fukuda, Katsunori Shiihara, Kazuo Sudo, Takeshi Maehara, Yasuo Morishima, Hiromi Kato, Hiroya Ichikawa

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, 191-195, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54836

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54836

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Topics: Laser welding, Nuclear reactors, Welding, Welding equipment, Maintenance, Nozzles, Nuclear power stations, Pressurized water reactors, Temperature, Alloy steel

Proceedings Papers

Development of Large Size Moisture Separator Reheater for Up to 1700 MW PWR Class

Issaku Fujita, Teruaki Sakata, Toshiki Kojima

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 81-90, May 17–21, 2010

Paper No: ICONE18-29157

DOI: https://doi.org/10.1115/ICONE18-29157

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Topics: Pressurized water reactors, Molten salt reactors, Flow (Dynamics), Steam, Computational fluid dynamics, Pressure, Pressure drop, Turbines, Corrosion, Design

Proceedings Papers

Thermal Hydraulic Analysis Towards a Robust Design of Leak Collection Tray for Pool Type Sodium Cooled Fast Reactors

Anil Kumar Sharma, K. Velusamy, N. Kasinathan, P. Chellapandi, S. C. Chetal, Baldev Raj

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 3, 421-428, May 17–21, 2010

Paper No: ICONE18-29294

DOI: https://doi.org/10.1115/ICONE18-29294

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Topics: Design, Fast neutron reactors, Leakage, Sodium, Fusibles (Textiles), Pipelines, Drainage, Fire, Metals, Oxygen

Proceedings Papers

An Analytical Method for Modeling Two-Phase Gravity-Driven Drainage Systems in BOP Applications

Robert Stakenborghs, Michael L. Morgan, Jr.

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 345-354, May 17–21, 2010

Paper No: ICONE18-30261

DOI: https://doi.org/10.1115/ICONE18-30261

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Topics: Drainage, Gravity (Force), Modeling, Transients (Dynamics), Design, Computer simulation, Feedwater, Flow (Dynamics), Molten salt reactors, Nuclear power

Proceedings Papers

Experimental Measurements of Eddy Current Signal From SG Tubes of Fast Breeder Reactor Covered by a Thin Sodium Layer Using a SG Mock-Up

Toshihiko Yamaguchi, Ovidiu Mihalache, Masashi Ueda, Shinya Miyahara

Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 605-613, July 12–16, 2009

Paper No: ICONE17-75607

DOI: https://doi.org/10.1115/ICONE17-75607

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Topics: Breeder reactors, Eddies (Fluid dynamics), Signals, Sodium, Drainage, Plates (structures), Temperature, Welded joints, Wetting, Alloys

NARROW

PTV Measurement of Whole-Field Monolayer Pebble Flow in Two-Dimensional Silo

Design and Comparison of Drainage Technology Scheme for Multi-Purpose Modular Small Reactor Science and Technology Demonstration Project

Experimental Study on Bubble Bursting and Droplet Releasing Characteristics Under Different Liquid Phase Conditions

An Experimental Study on Freeze Valve Performance in a Molten Salt Reactor

Root Cause Analysis of Pipeline Rupture in the Condensate Extraction System of Nuclear Power Plant

Preliminary Experimental Study on Erosion-Corrosion Behavior of Second Loop Pipeline in Nuclear Power Plant With Vapor Liquid Two Phase Flow

An Experimental Investigation on Drainage Performance of a Drain Device in a Steam Generator of PWR

Numerical Investigation on Critical Submerged Depth During Draining From Cylindrical Tanks

Experimental Study on Model Development for Liquid Accumulation in Steam Generator U-Tube (First Report) Condensing Counter-Current Flow in Single Vertical Pipe

Flow Instability Inside Heat Transfer Tubes of Moisture Separator Reheater

Study on Operating Criteria of the Supersonic Steam Injector

Study on Controlling Condensation Heat Transfer by Using Functionalized Heat Transfer Surface

Scaling Analysis of the Pressurizer Surge Line in Nuclear Plant Integral Test Facilities

Slug Flow Main Parameters in a Combined Inclined Up and Down Two-Phase Flow

Experiments and Simulations on the Steady-State and Transient Behavior of Gas/Liquid Interfaces in Impulse Pipes for Hydrostatic Level Measurements

Underwater Laser Beam Welding for Nuclear Reactors

Development of Large Size Moisture Separator Reheater for Up to 1700 MW PWR Class

Thermal Hydraulic Analysis Towards a Robust Design of Leak Collection Tray for Pool Type Sodium Cooled Fast Reactors

An Analytical Method for Modeling Two-Phase Gravity-Driven Drainage Systems in BOP Applications

Experimental Measurements of Eddy Current Signal From SG Tubes of Fast Breeder Reactor Covered by a Thin Sodium Layer Using a SG Mock-Up

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