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Proceedings Papers

Experience of Xenon Oscillation During an Initial Physics Test of UCN Unit 5 in Korea

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Yong Rae Kim, Tae Young Choi, Sun Ho Shin, Ki Bong Seong
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 173-175, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25237
https://doi.org/10.1115/PVP2010-25237
View Paper titled, Experience of Xenon Oscillation During an Initial Physics Test of UCN Unit 5 in Korea
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Topics: Oscillations, Physics, Cycles, Rods, Stability, Steady state
Proceedings Papers

The Effect of OBE Elimination on Class 1 Piping Systems

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Il Kwun Nam, Seok Hwan Hur, Dong Bum Oh
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 23-30, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25511
https://doi.org/10.1115/PVP2010-25511
View Paper titled, The Effect of OBE Elimination on Class 1 Piping Systems
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Topics: Piping systems, Design, Nuclear power stations, ASME Standards, Electricity (Physics), Engineering standards, Health and safety, Nuclear industry, Nuclear reactor coolants, Pipes
Proceedings Papers

Improvement of Mechanical Rebar Splices for N.P.P. Construction

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Jin-Gyu Lee, Young-Tae Ju, Jang-Kyu Choi, Sang-Gu Kim
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 51-54, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25256
https://doi.org/10.1115/PVP2010-25256
View Paper titled, Improvement of Mechanical Rebar Splices for N.P.P. Construction
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Topics: Construction, Reinforcing bar splices, Filler metals, Nuclear construction, Nuclear power stations
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

Core Design Experience to Adopt Long Term (18-Month) Cycle Operation Strategy From Initial Core

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Dong-Chul Jung, Ki Bong Seong
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 15-21, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25502
https://doi.org/10.1115/PVP2010-25502
View Paper titled, Core Design Experience to Adopt Long Term (18-Month) Cycle Operation Strategy From Initial Core
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Topics: Cycles, Design, Fuel rods, Oscillations, Construction, Fuels, Manufacturing, Neutron flux, Nuclear power stations, Pressurized water reactors
Proceedings Papers

Assessment of Interaction Effect Between Two Aligned Surface Cracks in Elbows Subjected to Internal Pressure

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Han-Beom Seo, Jae-Boong Choi, Young-Jin Kim, Yoon-Suk Chang, Hyun-Su Kim
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 113-118, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25604
https://doi.org/10.1115/PVP2010-25604
View Paper titled, Assessment of Interaction Effect Between Two Aligned Surface Cracks in Elbows Subjected to Internal Pressure
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Topics: Pressure, Surface cracks, Fracture (Materials), Fitness-for-service, Pipes, ASME Standards, Engineering standards, Finite element analysis, Plates (structures), Power stations
Proceedings Papers

Seismic Analysis Study of the HP Turbine Steam Supply Piping for APR1400

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Joon Ho Lee, In Yeung Kim, Jae Hwan Bae
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 31-36, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25550
https://doi.org/10.1115/PVP2010-25550
View Paper titled, Seismic Analysis Study of the HP Turbine Steam Supply Piping for APR1400
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Topics: Pipes, Seismic analysis, Steam, Turbines, Damping, Piping systems, Containment buildings, Excitation, High pressure (Physics), Modal analysis
Proceedings Papers

Conformity Assessment of the ITER Vacuum Vessel With the Requirements of the French Order for Nuclear Pressure Equipment

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Andre´ Weyn, Guy Vast, Erick Ru¨tze, Willy Wijns
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 167-170, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-26051
https://doi.org/10.1115/PVP2010-26051
View Paper titled, Conformity Assessment of the ITER Vacuum Vessel With the Requirements of the French Order for Nuclear Pressure Equipment
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Topics: Conformity assessment, Pressure equipment, Vacuum, Vessels, Safety, Design, Hazard analysis, In-service inspection, Manufacturing, Uncertainty
Proceedings Papers

Mechanical Property Changes Related to Through-Wall Attenuation of Neutron Irradiation Embrittlement

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W. Server, M. Brumovsky´, M. Kytka, N. Soneda, J. Spanner
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 135-141, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25842
https://doi.org/10.1115/PVP2010-25842
View Paper titled, Mechanical Property Changes Related to Through-Wall Attenuation of Neutron Irradiation Embrittlement
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Topics: Embrittlement, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Copper, Steel, Atoms, Fluence (Radiation measurement), Fracture toughness, Phase transition temperature
Proceedings Papers

Verification of the Output Signal Change of Control Rod Position Indicator at the End of Its Life Time

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Je-Yong Yu, Ji-Ho Kim, Hyung Huh, Myong-Hwan Choi, Dong-Seong Sohn
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 1-5, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25236
https://doi.org/10.1115/PVP2010-25236
View Paper titled, Verification of the Output Signal Change of Control Rod Position Indicator at the End of Its Life Time
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Topics: Signals, Magnets, Boron, Heating, Pressure, Design, Manufacturing, Nuclear power, Safety, Switches
Proceedings Papers

Regulatory Experience of Leak-Before-Break (LBB) Technology to the High Energy Piping Systems in Korea

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Yeon-Ki Chung, Jin-Su Kim, Hae-Dong Chung, Young-Hwan Choi
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 155-158, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25656
https://doi.org/10.1115/PVP2010-25656
View Paper titled, Regulatory Experience of Leak-Before-Break (LBB) Technology to the High Energy Piping Systems in Korea
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Topics: Leak-before-break, Piping systems, Fracture (Materials), Leakage, Pipes, Design, Materials properties, Pressurized water reactors, Stability, Stress
Proceedings Papers

Development of APESS Software for Power Plant Simulation

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Kihyun Lee, Kwanghun Jeong, Woowon Jeon, Younghoon Bae, Dongsu Lee
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 193-197, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25544
https://doi.org/10.1115/PVP2010-25544
View Paper titled, Development of APESS Software for Power Plant Simulation
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Topics: Computer software, Power stations, Simulation, Momentum, Algebra, Control systems, Design, Emergencies, Energy conservation, Flow (Dynamics)
Proceedings Papers

Advanced Construction Methods for New Nuclear Power Plants

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Dae-Yul Jung, Yoon-Kee Kang, Chang-Hyung You
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 55-59, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25369
https://doi.org/10.1115/PVP2010-25369
View Paper titled, Advanced Construction Methods for New Nuclear Power Plants
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Topics: Construction, Nuclear power stations, Industrial research, Nuclear construction, Nuclear power, Reinforcing bar splices, Three-dimensional computer-aided design
Proceedings Papers

Microstructural Changes Related to Through-Wall Attenuation of Neutron Irradiation Embrittlement

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Naoki Soneda, Kenji Nishida, Kenji Dohi, Akiyoshi Nomoto, William L. Server, Milan Brumovsky, Milos Kytka, Jack Spanner
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 119-124, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25636
https://doi.org/10.1115/PVP2010-25636
View Paper titled, Microstructural Changes Related to Through-Wall Attenuation of Neutron Irradiation Embrittlement
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Topics: Embrittlement, Irradiation (Radiation exposure), Neutrons, Copper, Mechanical properties, Atoms, Fluence (Radiation measurement), Steel, Fracture toughness, Metals
Proceedings Papers

NSSS Design Features of Advanced Power Reactor Plus (APR + )

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Hae Yun Choi, Kwang Won Lee, Jong Tae Seo
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 37-43, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25586
https://doi.org/10.1115/PVP2010-25586
View Paper titled, NSSS Design Features of Advanced Power Reactor Plus (APR + )
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Topics: Design, Safety, Construction, Economics , Vessels, Accidents, Conceptual design, Cooling, Feedwater, Fluidic devices
Proceedings Papers

Mechanical Properties of SA508 Gr.4N Model Alloys as a High Strength RPV Steel

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Min-Chul Kim, Ki-Hyoung Lee, Bong-Sang Lee, Whung-Whoe Kim
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 143-148, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-26002
https://doi.org/10.1115/PVP2010-26002
View Paper titled, Mechanical Properties of SA508 Gr.4N Model Alloys as a High Strength RPV Steel
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Topics: Alloys, Fracture toughness, Grain size, Mechanical properties, Precipitation, Steel
Proceedings Papers

Development of In-Situ Monitoring Technique on a Crack of Steam Generator Tubing: The Effect of Thermal Treatment on the SCC of Alloy 600

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Hyun Young Chang, Heung Bae Park, Young Sik Kim, Yoon Young Jang
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 103-106, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25569
https://doi.org/10.1115/PVP2010-25569
View Paper titled, Development of In-Situ Monitoring Technique on a Crack of Steam Generator Tubing: The Effect of Thermal Treatment on the SCC of Alloy 600
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Topics: Alloys, Boilers, Fracture (Materials), Tubing, Stress corrosion cracking, Corrosion, Noise (Sound), Grain boundaries, Heat treating (Metalworking), Cracking (Materials)
Proceedings Papers

Korean Regulatory Experience on PWSCC in Korean NPP

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Kyung-Cho Kim, Sung-bu Choi, Koo-Kab Chung, Hae-Dong Chung
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 159-165, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25929
https://doi.org/10.1115/PVP2010-25929
View Paper titled, Korean Regulatory Experience on PWSCC in Korean NPP
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Topics: Nuclear power stations, Alloys, Nozzles, Fracture (Materials), Cracking (Materials), Fracture (Process), Fittings, Indium alloys, Inspection, Instrumentation
Proceedings Papers

The Application of Optimized Commissioning Schedule

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Yong Ro Lee
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 199-204, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25560
https://doi.org/10.1115/PVP2010-25560
View Paper titled, The Application of Optimized Commissioning Schedule
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Topics: Delays, Fracture toughness, Nuclear power stations, Optimization
Proceedings Papers

Ensuring the Performance of Nuclear Reactor Pressure Vessels for Long-Time Service

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Randy K. Nanstad, G. Robert Odette, Mikhail A. Sokolov
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 9, 125-133, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25832
https://doi.org/10.1115/PVP2010-25832
View Paper titled, Ensuring the Performance of Nuclear Reactor Pressure Vessels for Long-Time Service
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Topics: Annealing, Databases, Embrittlement, Fluence (Radiation measurement), Fracture mechanics, Irradiation (Radiation exposure), Light water reactors, Neutrons, Nickel, Nuclear power stations