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Proceedings Papers

Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles

Osama Elbanhawy, Marwan Hassan, Atef Mohany, Hossam Kishawy
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A007, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-62412
https://doi.org/10.1115/PVP2021-62412
View Paper titled, Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles
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Topics: Dynamics (Mechanics), Fuel rods, Irradiation (Radiation exposure), Fuels, Flow (Dynamics), Constitutive equations, Coolants, Dynamic response, Mechanical properties, Pressure
Proceedings Papers

Evaluation of Creep Properties of Alloy 690 Steam Generator Tubes at High Temperature Using Tube Specimen

Jongmin Kim, Woogon Kim, Minchul Kim
Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A018, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93498
https://doi.org/10.1115/PVP2019-93498
View Paper titled, Evaluation of Creep Properties of Alloy 690 Steam Generator Tubes at High Temperature Using Tube Specimen
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Topics: Alloys, Boilers, Creep, High temperature, High temperature creep, Rupture, Accidents, Containment, Corrosion resistance, Failure
Proceedings Papers

Plastic Collapse Evaluation of Fuel Channel Assembly in Pressurized Heavy Water Reactor

Jun Hyeok Choi, Seok Jun Kang, Jae-Boong Choi
Proc. ASME. PVP2018, Volume 5: High-Pressure Technology; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Rudy Scavuzzo Student Paper Symposium and 26th Annual Student Paper Competition, V005T10A010, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84463
https://doi.org/10.1115/PVP2018-84463
View Paper titled, Plastic Collapse Evaluation of Fuel Channel Assembly in Pressurized Heavy Water Reactor
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Topics: Collapse, Fuels, Heavy water reactors, Manufacturing, High temperature, Coolants, Fracture (Materials), Boiling, Creep, Finite element analysis
Proceedings Papers

Nuclear-Related Materials and Technology Research at ANSTO

Michael Law, Philip J. Bendeich, Ondrej Muránsky, Warwick M. Payten, Cory J. Hamelin
Proc. ASME. PVP2016, Volume 6B: Materials and Fabrication, V06BT06A019, July 17–21, 2016
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-63686
https://doi.org/10.1115/PVP2016-63686
View Paper titled, Nuclear-Related Materials and Technology Research at ANSTO
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Topics: Cycles, Fusion reactors, Materials characterization, Modeling, Molecular dynamics, Nuclear fission, Nuclear power, Nuclear power stations, Power stations, Radiation (Physics)
Proceedings Papers

Characterization of Advanced Steels as Accident Tolerant Cladding for Light Water Reactor Nuclear Fuel

Raul B. Rebak
Proc. ASME. PVP2015, Volume 6B: Materials and Fabrication, V06BT06A006, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45652
https://doi.org/10.1115/PVP2015-45652
View Paper titled, Characterization of Advanced Steels as Accident Tolerant Cladding for Light Water Reactor Nuclear Fuel
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Topics: Accidents, Cladding systems (Building), Light water reactors, Nuclear fuels, Steel, Alloys, Fuels, Aluminum, Steam, Chemical kinetics
Proceedings Papers

Commissioning Tests for an Experimental Study of Steam Generator Tube Loading During Blowdown

Ouajih Hamouda, David S. Weaver, Jovica Riznic
Proc. ASME. PVP2013, Volume 4: Fluid-Structure Interaction, V004T04A074, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97809
https://doi.org/10.1115/PVP2013-97809
View Paper titled, Commissioning Tests for an Experimental Study of Steam Generator Tube Loading During Blowdown
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Topics: Boilers, Transients (Dynamics), Accidents, Radioactive substances, Boiling, Containment, Data collection, Design, Dynamics (Mechanics), Fluids
Proceedings Papers

TRISO Particle and Beryllium Pebble Thermo-Mechanical Response in a Fusion/Fission Engine for Incineration of Weapons Grade Plutonium

M. Caro, P. DeMange, J. Marian, A. Caro
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B, 787-791, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25014
https://doi.org/10.1115/PVP2010-25014
View Paper titled, TRISO Particle and Beryllium Pebble Thermo-Mechanical Response in a Fusion/Fission Engine for Incineration of Weapons Grade Plutonium
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Topics: Engines, Nuclear fission, Particulate matter, Thermomechanics, Weapons, Fuels, Neutrons, Design, Materials properties, Atoms
Proceedings Papers

Finite Element Analysis for Local Creep of a Tube Coolant Piping System in Light Water Reactor Due to Local Heating Under Severe Accident Condition

Seiya Hagihara, Noriyuki Miyazaki
Proc. ASME. PVP2002, Design and Analysis of Piping, Vessels, and Components, 25-32, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1260
https://doi.org/10.1115/PVP2002-1260
View Paper titled, Finite Element Analysis for Local Creep of a Tube Coolant Piping System in Light Water Reactor Due to Local Heating Under Severe Accident Condition
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Topics: Accidents, Coolants, Creep, Finite element analysis, Heating, Light water reactors, Piping systems, Pipes, Damage, High temperature
Proceedings Papers

Integrated Leak Rate Testing of Containments: A Regulatory Perspective

Hans Ashar, Eugene Imbro, David Terao
Proc. ASME. PVP2002, Piping and Component Analysis and Diagnosis, 83-87, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1520
https://doi.org/10.1115/PVP2002-1520
View Paper titled, Integrated Leak Rate Testing of Containments: A Regulatory Perspective
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Topics: Leakage, Testing, Containment, Risk, Accidents, Nuclear reactor coolants, Risk-based decision making, Water, Acceptance criteria, Coolants
Proceedings Papers

Surveillance Specimen Programs for WWER Type Reactors

Milan Brumovsky
Proc. ASME. PVP2005, Volume 7: Operations, Applications, and Components, 23-31, July 17–21, 2005
Publisher: American Society of Mechanical Engineers
Paper No: PVP2005-71475
https://doi.org/10.1115/PVP2005-71475
View Paper titled, Surveillance Specimen Programs for WWER Type Reactors
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Topics: Surveillance, Reactor vessels, Vessels, Engineering standards, Water, ASME Standards, ASTM International, China, Manufacturing, Mechanical properties
Proceedings Papers

Assessment of Limit Loads for Circumferential Cracks in Steam Generator Tube Considering Constraining Effect of Tube Support

Hyun Su Kim, Jong Sung Kim, Tae Eun Jin, Hong Deok Kim, Han Sub Chung
Proc. ASME. PVP2005, Volume 3: Design and Analysis, 363-368, July 17–21, 2005
Publisher: American Society of Mechanical Engineers
Paper No: PVP2005-71308
https://doi.org/10.1115/PVP2005-71308
View Paper titled, Assessment of Limit Loads for Circumferential Cracks in Steam Generator Tube Considering Constraining Effect of Tube Support
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Topics: Boilers, Fracture (Materials), Stress, Boundary-value problems, Nuclear power stations, Finite element analysis, Heat, Heat exchangers, Nuclear fission, Plates (structures)