The Korea Atomic Energy Research Institute (KAERI) and Brookhaven National Laboratory (BNL) are collaborating to develop seismic capability evaluation technology for degraded structures and passive components (SPCs) under a multi-year research agreement. To better understand the status and characteristics of degradation of SPCs in nuclear power plants (NPPs), the first step in this multi-year research effort was to identify and evaluate degradation occurrences of SPCs in U.S. NPPs. This was performed by reviewing recent publicly available information sources to identify and evaluate the characteristics of degradation occurrences and then comparing the information to the observations in the past. Ten categories of SPCs that are applicable to Korean NPPs were identified, comprising of anchorage, concrete, containment, exchanger, filter, piping system, reactor pressure vessel, structural steel, tank, and vessel. Software tools were developed to expedite the review process. Results from this review effort were compared to previous data in the literature to characterize the overall degradation trends.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4352-9
PROCEEDINGS PAPER
Review of Recent Aging-Related Degradation Occurrences of Structures and Passive Components in U.S. Nuclear Power Plants
Jinsuo Nie,
Jinsuo Nie
Brookhaven National Laboratory, Upton, NY
Search for other works by this author on:
Joseph I. Braverman,
Joseph I. Braverman
Brookhaven National Laboratory, Upton, NY
Search for other works by this author on:
Charles H. Hofmayer,
Charles H. Hofmayer
Brookhaven National Laboratory, Upton, NY
Search for other works by this author on:
Young-Sun Choun,
Young-Sun Choun
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
Min Kyu Kim,
Min Kyu Kim
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
In-Kil Choi
In-Kil Choi
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Search for other works by this author on:
Jinsuo Nie
Brookhaven National Laboratory, Upton, NY
Joseph I. Braverman
Brookhaven National Laboratory, Upton, NY
Charles H. Hofmayer
Brookhaven National Laboratory, Upton, NY
Young-Sun Choun
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Min Kyu Kim
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
In-Kil Choi
Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
Paper No:
ICONE17-75814, pp. 235-244; 10 pages
Published Online:
February 25, 2010
Citation
Nie, J, Braverman, JI, Hofmayer, CH, Choun, Y, Kim, MK, & Choi, I. "Review of Recent Aging-Related Degradation Occurrences of Structures and Passive Components in U.S. Nuclear Power Plants." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications. Brussels, Belgium. July 12–16, 2009. pp. 235-244. ASME. https://doi.org/10.1115/ICONE17-75814
Download citation file:
8
Views
Related Proceedings Papers
Related Articles
The Fabulous Nuclear Odyssey of Belgium
J. Pressure Vessel Technol (June,2009)
Heavy-Section Steel Technology Program: Fracture Issues (Survey Paper)
J. Pressure Vessel Technol (August,1992)
PBMR-A Future Failsafe Gas Turbine Nuclear Power Plant?
Mechanical Engineering (August,2011)
Related Chapters
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 1, Second Edition
Subsection NCA—General Requirements for Division 1 and Division 2
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition
Iwe and Iwl
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Fourth Edition