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Proceedings Papers

RPV Irradiation Surveillance Programmes in China

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Shuo Zhang, Haisheng Zhang, Kai Sun
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A025, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93068
https://doi.org/10.1115/PVP2019-93068
View Paper titled, RPV Irradiation Surveillance Programmes in China
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Topics: China, Irradiation (Radiation exposure), Surveillance, Pressurized water reactors, Safety, Nuclear power, Nuclear power stations, Construction, Design, Embrittlement
Proceedings Papers

Finite Element Verification of Engineering Equations for Prediction of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors

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Preeti Doddihal, Dennis Kawa, Douglas Scarth, Yu Chen
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A013, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93671
https://doi.org/10.1115/PVP2019-93671
View Paper titled, Finite Element Verification of Engineering Equations for Prediction of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors
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Topics: Annulus, Finite element analysis, Nuclear reactors, Fracture (Materials), Fracture (Process), Strips, Fuels, Irradiation (Radiation exposure), Pressure, Stress
Proceedings Papers

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

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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

Improved Engineering Process-Zone Model for Evaluation of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors

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Cheng Liu, Leonid Gutkin, Douglas Scarth
Proc. ASME. PVP2017, Volume 6A: Materials and Fabrication, V06AT06A040, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-66193
https://doi.org/10.1115/PVP2017-66193
View Paper titled, Improved Engineering Process-Zone Model for Evaluation of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors
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Topics: Annulus, Nuclear reactors, Pressure, Stress, Design, Fuels, Separation (Technology), Traction, Damage, Displacement
Proceedings Papers

Engineering Process-Zone Model for Evaluation of Structural Strength of Fuel Channel Annulus Spacers in CANDU Nuclear Reactors

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Douglas Scarth, Steven Xu, Cheng Liu
Proc. ASME. PVP2017, Volume 6A: Materials and Fabrication, V06AT06A041, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-66194
https://doi.org/10.1115/PVP2017-66194
View Paper titled, Engineering Process-Zone Model for Evaluation of Structural Strength of Fuel Channel Annulus Spacers in CANDU Nuclear Reactors
Open the PDF for Engineering Process-Zone Model for Evaluation of Structural Strength of Fuel Channel Annulus Spacers in CANDU Nuclear Reactors in another window
Topics: Annulus, Fuels, Nuclear reactors, Pressure, Design, Load bearing capacity, Stress, Alloys, Damage, Engineering models
Proceedings Papers

Fracture Protection of CANDU Zr-2.5Nb Pressure Tubes With High Hydrogen Equivalent Concentration

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Preeti Doddihal, Douglas Scarth, Paula Mosbrucker, Steven Xu
Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A032, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-46000
https://doi.org/10.1115/PVP2015-46000
View Paper titled, Fracture Protection of CANDU Zr-2.5Nb Pressure Tubes With High Hydrogen Equivalent Concentration
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Topics: Fracture (Materials), Hydrogen, Pressure, Zirconium, Temperature, Fracture toughness, Heat, Alloys, Coolants, Corrosion
Proceedings Papers

Small Scale Burst Facility: Experimental Investigation of Fluid-Structure Interaction in a PHWR

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J. J. Baschuk, Alan West, B. W. Leitch
Proc. ASME. PVP2013, Volume 4: Fluid-Structure Interaction, V004T04A069, July 14–18, 2013
Publisher: American Society of Mechanical Engineers
Paper No: PVP2013-97422
https://doi.org/10.1115/PVP2013-97422
View Paper titled, Small Scale Burst Facility: Experimental Investigation of Fluid-Structure Interaction in a PHWR
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Topics: Fluid structure interaction, Heavy water reactors, Fuels, Pressure, Modeling, Test facilities, Uranium, Vessels, Water, Accidents
Proceedings Papers

LBB Under Beyond Design Basis Seismic Loading

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Tao Zhang, Frederick W. Brust, Gery Wilkowski, Heqin Xu, Alfredo A. Betervide, Oscar Mazzantini
Proc. ASME. PVP2012, Volume 8: Seismic Engineering, 55-64, July 15–19, 2012
Publisher: American Society of Mechanical Engineers
Paper No: PVP2012-78581
https://doi.org/10.1115/PVP2012-78581
View Paper titled, LBB Under Beyond Design Basis Seismic Loading
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Topics: Design, Fracture (Materials), Nuclear power stations, Pipes, Earthquakes, Heavy water reactors, Leakage, Water, Construction, Dynamic response
Proceedings Papers

Robust LBB Analyses for Atucha II Nuclear Plant

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G. Wilkowski, B. Brust, T. Zhang, G. Hattery, S. Kalyanam, D.-J. Shim, E. Kurth, Y. Hioe, M. Uddin, J. J. Johnson, O. R. Maslenikov, A. Gu¨rpinar, A. P. Asfura, B. Sumodobila, A. A. Betervide, O. Mazzantini
Proc. ASME. PVP2011, Volume 1: Codes and Standards, 107-120, July 17–21, 2011
Publisher: American Society of Mechanical Engineers
Paper No: PVP2011-57939
https://doi.org/10.1115/PVP2011-57939
View Paper titled, Robust LBB Analyses for Atucha II Nuclear Plant
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Topics: Nuclear power stations, Stress, Design, Fracture (Materials), Emergency core cooling systems, Leakage, Pipes, Construction, Displacement, Residual stresses
Proceedings Papers

Heavy Components Replacement in Nuclear Power Plants: Guidelines and Experiences

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Ki Sig Kang
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 7, 229-235, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25875
https://doi.org/10.1115/PVP2010-25875
View Paper titled, Heavy Components Replacement in Nuclear Power Plants: Guidelines and Experiences
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Topics: Nuclear power stations, Pressurized water reactors, Pipes, Reactor vessels, Boilers, Boiling water reactors, Fatigue, Heavy water reactors, Nuclear power, Nuclear reactor coolants
Proceedings Papers

A Study on Improvement Through Analysis of Cold Hydrostatic Test Cases in Korea Nuclear Power Plants

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Ki Sang Song, Kyeong Sik Chae
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 185-192, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25298
https://doi.org/10.1115/PVP2010-25298
View Paper titled, A Study on Improvement Through Analysis of Cold Hydrostatic Test Cases in Korea Nuclear Power Plants
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Topics: Hydrostatic testing, Nuclear power stations, Pressure, Design, Pumps, Heavy water reactors, Nuclear reactor coolants, Construction, Control systems, Errors
Proceedings Papers

Analysis of a PHWR Outlet Feeder Vibration Due to Random Turbulence-Induced Excitation

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Y. Han, V. P. Janzen, B. A. W. Smith, T. Godet
Proc. ASME. PVP2007, Volume 4: Fluid-Structure Interaction, 503-512, July 22–26, 2007
Publisher: American Society of Mechanical Engineers
Paper No: PVP2007-26772
https://doi.org/10.1115/PVP2007-26772
View Paper titled, Analysis of a PHWR Outlet Feeder Vibration Due to Random Turbulence-Induced Excitation
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Topics: Excitation, Heavy water reactors, Turbulence, Vibration, Finite element analysis, Flow (Dynamics), Pipes, Stress, Coolants, Corrosion
Proceedings Papers

Study on Limits of Height-to-Width Ratio for Base Isolated Buildings Under Earthquake

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Hong-Nan Li, Xiang-Xiang Wu
Proc. ASME. PVP2002, Seismic Engineering, Volume 2, 135-142, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1438
https://doi.org/10.1115/PVP2002-1438
View Paper titled, Study on Limits of Height-to-Width Ratio for Base Isolated Buildings Under Earthquake
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Topics: Earthquakes, Structures, Heavy water reactors, Bearings, Rubber, Soil, Engineers, Excitation, Stiffness, Structural design
Proceedings Papers

Experimental Investigations on Effects of Simulated Seismic Loading on LBB Assessment of High Energy Piping

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Suneel K. Gupta, Vivek Bhasin, K. K. Vaze, A. K. Ghosh, H. S. Kushwaha
Proc. ASME. PVP2005, Volume 6: Materials and Fabrication, 601-616, July 17–21, 2005
Publisher: American Society of Mechanical Engineers
Paper No: PVP2005-71310
https://doi.org/10.1115/PVP2005-71310
View Paper titled, Experimental Investigations on Effects of Simulated Seismic Loading on LBB Assessment of High Energy Piping
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Topics: Pipes, Fracture (Materials), Stress, Design, Earthquakes, Heavy water reactors, Accidents, ASTM International, Carbon steel, Cycles