In the nuclear industry, demands on the structural integrity reliability of metal components are always increasing. The quantification of allowable defects in pressure vessels should therefore draw on advanced structural integrity assessment procedures. In the UK, R6 [1] is the main procedures used for defect tolerance assessment (DTA). In this paper, the overall evaluation procedure of DTA using R6 applied to the Main Steam (MS) nozzle crotch corner of the Advanced Boiling Water Reactor (ABWR) is presented. At the nozzle crotch corner region, high stresses, including through-wall bending stresses from the local structural discontinuity, were present. These bending stresses have been categorised as secondary. R6 conservatively implies such bending stresses may need to be categorised as primary, to allow for the possibility of elastic follow-up. To support application as a secondary stress, an elastic-plastic finite element analysis has been performed to evaluate the J-integral for the nozzle crotch corner. The resulting values of J, when compared to the stress intensity factor and collapse solutions used for the assessment, showed that treating the bending stress as secondary maintained sufficient margin, indicating conservatism. Finally, the DTA results of the nozzle crotch corner are presented to determine the defect tolerance criteria. This includes calculating the limiting defect size at the start of plant life when considering the end of life critical defect size and through life Fatigue Crack Growth (FCG).
Skip Nav Destination
ASME 2016 Pressure Vessels and Piping Conference
July 17–21, 2016
Vancouver, British Columbia, Canada
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5036-7
PROCEEDINGS PAPER
Defect Tolerance Assessment for ABWR Nozzle Crotch Corner Available to Purchase
Fumihito Hirokawa,
Fumihito Hirokawa
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Japan
Search for other works by this author on:
Masaaki Hayashi,
Masaaki Hayashi
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Japan
Search for other works by this author on:
Minoru Masuda,
Minoru Masuda
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Japan
Search for other works by this author on:
Yasuhiro Mabuchi,
Yasuhiro Mabuchi
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Japan
Search for other works by this author on:
Yukinori Yamamoto,
Yukinori Yamamoto
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Japan
Search for other works by this author on:
Fuminori Iwamatsu,
Fuminori Iwamatsu
Hitachi, Ltd., Hitachi, Japan
Search for other works by this author on:
Katsumasa Miyazaki,
Katsumasa Miyazaki
Hitachi, Ltd., Hitachi, Japan
Search for other works by this author on:
David Johnson
David Johnson
AMEC Foster Wheeler, Knutsford, UK
Search for other works by this author on:
Fumihito Hirokawa
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Japan
Masaaki Hayashi
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Japan
Minoru Masuda
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Japan
Yasuhiro Mabuchi
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Japan
Yukinori Yamamoto
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Japan
Fuminori Iwamatsu
Hitachi, Ltd., Hitachi, Japan
Katsumasa Miyazaki
Hitachi, Ltd., Hitachi, Japan
David Johnson
AMEC Foster Wheeler, Knutsford, UK
Paper No:
PVP2016-63823, V01BT01A006; 9 pages
Published Online:
December 1, 2016
Citation
Hirokawa, F, Hayashi, M, Masuda, M, Mabuchi, Y, Yamamoto, Y, Iwamatsu, F, Miyazaki, K, & Johnson, D. "Defect Tolerance Assessment for ABWR Nozzle Crotch Corner." Proceedings of the ASME 2016 Pressure Vessels and Piping Conference. Volume 1B: Codes and Standards. Vancouver, British Columbia, Canada. July 17–21, 2016. V01BT01A006. ASME. https://doi.org/10.1115/PVP2016-63823
Download citation file:
22
Views
Related Proceedings Papers
Related Articles
An Approach to Derive Primary Bending Stress From Finite Element Analysis for Pressure Vessels and Applications in Structural Design
J. Pressure Vessel Technol (December,2010)
Parametric FEA Study of Burst Pressure of Cylindrical Shell Intersections
J. Pressure Vessel Technol (June,2010)
Finite Element Modeling of Fatigue Damage Using a Continuum Damage Mechanics Approach
J. Pressure Vessel Technol (May,2005)
Related Chapters
Openings
Guidebook for the Design of ASME Section VIII Pressure Vessels
Subsection NB—Class 1 Components
Companion Guide to the ASME Boiler & Pressure Vessel Codes, Volume 1 Sixth Edition
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition