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Proceedings Papers

Development of Ultrasonic Measurement System for Shape and 2D Velocity Field Using Ultrasonic Velocity Profiler and Total Focusing Methods

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Zeliang Zhang, Tianrun Liu, Munkhbat Batsaikhan, Hideharu Takahashi, Hiroshige Kikura
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A049, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64510
https://doi.org/10.1115/ICONE28-64510
View Paper titled, Development of Ultrasonic Measurement System for Shape and 2D Velocity Field Using Ultrasonic Velocity Profiler and Total Focusing Methods
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Topics: Fuels, Fukushima nuclear disaster, Japan, 2011, Nuclear decommissioning, Nuclear power stations, Shapes, Transducers, Ultrasonic measurement, Accidents, Radiation (Physics), Water leakage
Proceedings Papers

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

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Xinjie Deng, Xuewu Cao
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A021, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81314
https://doi.org/10.1115/ICONE26-81314
View Paper titled, Study on Hydrogen Migration in Small Water Leak of Sodium-Cooled Fast Reactor
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Topics: Hydrogen, Sodium fast reactors, Water leakage, Sodium, Circuits, Water, Leakage, Boilers, Fracture (Materials), Heat
Proceedings Papers

Development of Numerical Simulation Method to Evaluate Heat Transfer Performance of Air Around Fuel Debris: Part 2 — Validation of JUPITER for Free Convection Heat Transfer

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Shinichiro Uesawa, Susumu Yamashita, Mitsuhiko Shibata, Hiroyuki Yoshida
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A097, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67517
https://doi.org/10.1115/ICONE25-67517
View Paper titled, Development of Numerical Simulation Method to Evaluate Heat Transfer Performance of Air Around Fuel Debris: Part 2 — Validation of JUPITER for Free Convection Heat Transfer
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Topics: Computer simulation, Fuels, Heat transfer, Natural convection, Radiation (Physics), Cooling, Containment vessels, Evaluation methods, Flow visualization, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

A Study on the Straight Double-Walled Tube Steam Generator Design Against Sodium-Water Reaction in DECs

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Hironori Kanda, Yasuhiro Enuma, Satoshi Futagami, Masaya Kawamura, Hiroshi Ushiki, Shinya Ogumo, Takashi Ichihara, Takashi Nakashima
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A009, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60156
https://doi.org/10.1115/ICONE24-60156
View Paper titled, A Study on the Straight Double-Walled Tube Steam Generator Design Against Sodium-Water Reaction in DECs
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Topics: Boilers, Design, Sodium, Water, Failure, Sodium fast reactors, Water leakage, Contact resistance, Temperature, Leakage
Proceedings Papers

A Remote Operated Quadruped Robot System for Investigation of Reactor Building

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Naotaka Suganuma, Takuya Uehara, Kenji Matsuzaki, Makoto Ochiai, Fujio Terai, Akira Tsuyuki, Itaru Chida
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T01A005, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30304
https://doi.org/10.1115/ICONE22-30304
View Paper titled, A Remote Operated Quadruped Robot System for Investigation of Reactor Building
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Topics: Robots, Vehicles, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Stairs, Cables, Disasters, Manipulators, Radiation (Physics), Water leakage
Proceedings Papers

Air Ingestion and Transport Testing in a Rotating Drum Raw Water Strainer

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Ludwig C. Haber, James Smith
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, 263-268, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55231
https://doi.org/10.1115/ICONE20-POWER2012-55231
View Paper titled, Air Ingestion and Transport Testing in a Rotating Drum Raw Water Strainer
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Topics: Testing, Water, Bubbles, Cooling, Flow (Dynamics), Lakes, Packing (Shipments), Packings (Cushioning), Suction, Filters
Proceedings Papers

Sodium and Steam Generator Leak Detection for Prototype Fast Breeder Reactor (PFBR)

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V. Vijayakumar, S. C. Chetal, K. Madhusoodanan, C. Paramasivan Pillai, M. Sakthivel, Uma Seshadri
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 2, 465-471, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49362
https://doi.org/10.1115/ICONE12-49362
View Paper titled, Sodium and Steam Generator Leak Detection for Prototype Fast Breeder Reactor (PFBR)
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Topics: Boilers, Breeder reactors, Engineering prototypes, Leakage, Sodium, Hydrogen, Temperature, Sensors, Concretes, Instrumentation
Proceedings Papers

Study of Thermal Influence on Tubes Due to Sodium-Water Reactions in LMFBR Steam Generator

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Hirotsugu Hamada, Akikazu Kurihara, Masahiro Nishimura
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 1, 239-248, April 25–29, 2004
Publisher: American Society of Mechanical Engineers
Paper No: ICONE12-49064
https://doi.org/10.1115/ICONE12-49064
View Paper titled, Study of Thermal Influence on Tubes Due to Sodium-Water Reactions in LMFBR Steam Generator
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Topics: Boilers, Liquid metal fast breeder reactors, Sodium, Water, Hydrogen, Temperature, Heat transfer, Flow (Dynamics), Accidents, Approximation
Proceedings Papers

Ligament Rupture Pressure of Fretted SG Tubes of PWRs

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Seong Sik Hwang, Man Kyo Jung, Hong Pyo Kim, Joung Soo Kim
Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 415-418, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89211
https://doi.org/10.1115/ICONE14-89211
View Paper titled, Ligament Rupture Pressure of Fretted SG Tubes of PWRs
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Topics: Pressure, Pressurized water reactors, Rupture, Fracture (Materials), Fracture (Process), Boilers, High pressure (Physics), Pumps, Safety, Temperature