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Proceedings Papers

Advancement of Reactor Coolant Pump (RCP) Performance Verification Test in KAERI

Yun-Je Cho, Yeon-Sik Kim, Seok Cho, Seok Kim, Byoung-Uhn Bae, Heung-June Chung, Young-Jung Youn, Jong-Kuk Park, Hae-Seob Choi, Woo-Jin Jeon, Bok-Deuk Kim, Tae-Soon Kwon, Chul-Hwa Song
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A047, July 7–11, 2014
Paper No: ICONE22-31075
https://doi.org/10.1115/ICONE22-31075
View Paper titled, Advancement of Reactor Coolant Pump (RCP) Performance Verification Test in KAERI
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Topics: Nuclear reactor coolants, Pumps, Flow (Dynamics), Pressure, Temperature, Transients (Dynamics), Errors, Flowmeters, Fluids, Resonance
Proceedings Papers

Sensitivity Analysis of the Response of PWR Containment During a Loss of Coolant Accident Using RELAP5-3D and MELCOR

Rodolfo Vaghetto, Andrew Franklin, Alessandro Vanni, Yassin A. Hassan
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A062, July 7–11, 2014
Paper No: ICONE22-31237
https://doi.org/10.1115/ICONE22-31237
View Paper titled, Sensitivity Analysis of the Response of PWR Containment During a Loss of Coolant Accident Using RELAP5-3D and MELCOR
Open the PDF for Sensitivity Analysis of the Response of PWR Containment During a Loss of Coolant Accident Using RELAP5-3D and MELCOR in another window
Topics: Accidents, Containment, Coolants, Pressurized water reactors, Sensitivity analysis, Discharge coefficient, Flow (Dynamics), Modeling, Nuclear reactors, Pressure
Proceedings Papers

Development of High Accurate Flow Nozzle for Feedwater Flowrate Measurement in Nuclear Power Plant

Noriyuki Furuichi, KarHooi Cheong, Yoshiya Terao, Shinichi Nakao, Keiji Fujita, Kazuo Shibuya
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A063, July 7–11, 2014
Paper No: ICONE22-30482
https://doi.org/10.1115/ICONE22-30482
View Paper titled, Development of High Accurate Flow Nozzle for Feedwater Flowrate Measurement in Nuclear Power Plant
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Topics: Feedwater, Flow (Dynamics), Nozzles, Nuclear power stations, Discharge coefficient, Reynolds number, Errors, Calibration, Flowmeters
Proceedings Papers

A Study of Venturi Tubes

Richard L. Wakeland
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 885-892, July 30–August 3, 2012
Paper No: ICONE20-POWER2012-55212
https://doi.org/10.1115/ICONE20-POWER2012-55212
View Paper titled, A Study of Venturi Tubes
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Topics: Venturi tubes, Discharge coefficient, Flow (Dynamics), Calibration, Design, Manufacturing, Reynolds number, Iron, Mechanical engineers, Nozzles
Proceedings Papers

Evaluation of a SGTR Accident in the Multi-Application Integrated Pressurized Water Reactor

Liguo Jiang, Minjun Peng, Jiange Liu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 915-920, May 17–21, 2010
Paper No: ICONE18-29953
https://doi.org/10.1115/ICONE18-29953
View Paper titled, Evaluation of a SGTR Accident in the Multi-Application Integrated Pressurized Water Reactor
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Topics: Accidents, Pressurized water reactors, Boilers, Rupture, Safety, Discharge coefficient, Flow (Dynamics), Heat, High pressure (Physics), Modeling
Proceedings Papers

Sensitivity Studies on Thermal-Hydraulic Behavior Associated With LOFT Total Loss-of-Feedwater Accident

Kyu Bok Lee, Heedo Lee, Hee Jin Ko, Ho Je Seong, Jae Sik Jeung, Chang Hyo Kim
Proc. ASME. ICONE12, 12th International Conference on Nuclear Engineering, Volume 3, 445-453, April 25–29, 2004
Paper No: ICONE12-49124
https://doi.org/10.1115/ICONE12-49124
View Paper titled, Sensitivity Studies on Thermal-Hydraulic Behavior Associated With LOFT Total Loss-of-Feedwater Accident
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Topics: Accidents, Feedwater, Transients (Dynamics), Boilers, Computers, Discharge coefficient, Fluids, Heat transfer, Heat transfer coefficients, Relief valves
Proceedings Papers

Prediction of Severe Accident Counter Current Natural Circulation Flows in the Hot Leg of a Pressurized Water Reactor

Christopher F. Boyd
Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 429-434, July 17–20, 2006
Paper No: ICONE14-89843
https://doi.org/10.1115/ICONE14-89843
View Paper titled, Prediction of Severe Accident Counter Current Natural Circulation Flows in the Hot Leg of a Pressurized Water Reactor
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Topics: Accidents, Flow (Dynamics), Pressurized water reactors, Boilers, Computational fluid dynamics, Discharge coefficient, Reactor vessels, Surges, Failure, Hydrogen