In nuclear power plants, RPV (Reactor Pressure Vessel) upper head CRDM (Control Rod Drive Mechanism) penetration tubes has been fabricated J-groove weld geometry. Recently, the incidences of cracking in Alloy 600 CRDM tubes and their associated welds have increased significantly. The cracking mechanism has been attributed to PWSCC (Pressurized Water Stress Corrosion Cracking) and has been shown to be driven by welding residual stresses and operational stresses in the weld region. Weld induced residual stress is main factor for crack growth. Therefore exact estimation of residual stress is important for reliable operating. In this point, we have been conducting detailed welding simulation analyses for Korea Nuclear Reactor Pressure Vessel to predict the magnitude of weld residual stresses in penetration tubes. In the present work, the FE (Finite Element) simulations were conducted to investigate the effects of tube geometry (location and ro/t) and material properties on the residual stresses in the J-groove weld for a different location of CRDM tubes. The variables of tube location included three (center-hole, intermediate and steepest side hill tube) inclination angles (Ψ). And this comparison was performed for different tube geometry (ro/t = 2, 3, 4), different yield strength (σo) of tube. In CRDM tube, when increases in tube inclination angle (Ψ), axial residual stress are gradually increased, but hoop residual stresses are decreased at the nearby weld root. In effect of tube radius and thickness, when the thickness of CRDM tubes increases the residual stresses are gradually decreased at the inner surface of tube. And there is no effect of CRDM tube radius (ro). In effect of plastic properties of Alloy 600 material in CRDM, when yield strength of the tube increases the axial residual stresses decreases but hoop residual stress increases.
Skip Nav Destination
ASME 2012 Pressure Vessels and Piping Conference
July 15–19, 2012
Toronto, Ontario, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5505-8
PROCEEDINGS PAPER
Prediction of Residual Stress Distribution for RPV CRDM Penetration Nozzles
Hong-Yeol Bae,
Hong-Yeol Bae
Korea University, Seoul, Korea
Search for other works by this author on:
Ju-Hee Kim,
Ju-Hee Kim
Korea Military Academy, Seoul, Korea
Search for other works by this author on:
Sung-Ho Lee,
Sung-Ho Lee
Korea Hydro and Nuclear Power Company, Daejeon, Korea
Search for other works by this author on:
Kyoungsoo Lee
Kyoungsoo Lee
Korea Hydro and Nuclear Power Company, Daejeon, Korea
Search for other works by this author on:
Hong-Yeol Bae
Korea University, Seoul, Korea
Yun-Jae Kim
Korea University, Seoul, Korea
Ju-Hee Kim
Korea Military Academy, Seoul, Korea
Sung-Ho Lee
Korea Hydro and Nuclear Power Company, Daejeon, Korea
Kyoungsoo Lee
Korea Hydro and Nuclear Power Company, Daejeon, Korea
Paper No:
PVP2012-78456, pp. 1165-1178; 14 pages
Published Online:
August 8, 2013
Citation
Bae, H, Kim, Y, Kim, J, Lee, S, & Lee, K. "Prediction of Residual Stress Distribution for RPV CRDM Penetration Nozzles." Proceedings of the ASME 2012 Pressure Vessels and Piping Conference. Volume 6: Materials and Fabrication, Parts A and B. Toronto, Ontario, Canada. July 15–19, 2012. pp. 1165-1178. ASME. https://doi.org/10.1115/PVP2012-78456
Download citation file:
8
Views
Related Proceedings Papers
Related Articles
Mechanical and Thermomechanical Elastic-Plastic Contact Analysis of Layered Media With Patterned Surfaces
J. Tribol (January,2004)
Improvement of Residual Stresses of Circumferential Joint of Pipe by Heat-Sink Welding
J. Pressure Vessel Technol (February,1986)
Transformation Plasticity and Residual Stresses in Single-Pass Repair Welds
J. Pressure Vessel Technol (February,1992)
Related Chapters
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
Part 2, Section II—Materials and Specifications
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition
Part 2, Section II—Materials and Specifications
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 1, Second Edition