Nuclear Engineering and Technology

  • 제44권3호
  • /
  • Pages.297-310
  • /
  • 2012
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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IDENTIFICATION AND ASSESSMENT OF AGING-RELATED DEGRADATION OCCURRENCES IN NUCLEAR POWER PLANTS

  • Choi, In-Kil (Korea Atomic Energy Research Institute) ;
  • Choun, Young-Sun (Korea Atomic Energy Research Institute) ;
  • Kim, Min-Kyu (Korea Atomic Energy Research Institute) ;
  • Nie, Jinsuo (Brookhaven National Laboratory) ;
  • Braverman, Joseph I. (Brookhaven National Laboratory) ;
  • Hofmayer, Charles H. (Brookhaven National Laboratory)
  • 투고 : 2010.09.15
  • 심사 : 2011.07.18
  • 발행 : 2012.04.25
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초록

Aging-related degradation of nuclear power plant components is an important aspect to consider in securing the long term safety of the plant, especially the seismic safety, since the degradation of the components affects not only their seismic capacity but their response. This can cause a change in the seismic margin of a component and the overall seismic safety of a system. To better understand the status and characteristics of degradation of components in Nuclear Power Plants (NPPs), the degradation occurrences of components in the U.S. NPPs were identified by reviewing recent publicly available information sources and the characteristics of these occurrences were evaluated and compared to observations from the past. Ten categories of components that are of high risk significance in Korean NPPs were identified, comprising anchorage, concrete, containment, exchanger, filter, piping systems, reactor pressure vessels, structural steel, tanks, and vessels. 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.

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참고문헌

  1. Young-Sun Choun, In-Kil Choi, and Jeong-Moon Seo, "Improvement of the Seismic Safety of Existing Nuclear Power Plants by an Increasing of the Component Seismic Capacity: A Case Study," Nuclear Engineering and Design, 238, pp. 1410-1420, 2008. https://doi.org/10.1016/j.nucengdes.2007.10.008
  2. Braverman, J.I., Hofmayer, C.H., Morante, R.J., Shteyngart, S., and Bezler, P., Assessmesnt of age-related degradation of structures and passive components for U.S. nuclear power plant, Brookhaven National Laboratory, NUREG/CR-6679, July 2000.
  3. Nie, J., Braverman, J., and Hofmayer, C., Choun, Y.S., Kim M.K., and Choi, I.K, Identification and Assessment of Recent Aging-Related Degradation Occurrences in U.S. Nuclear Power Plants, BNL Report-81741-2008 and KAERI/RR-2931/2008, 2008.
  4. U.S. Nuclear Regulatory Commission, 10 CFR 50.73, Licensee Event Report System.
  5. U.S. Nuclear Regulatory Commission, 10 CFR 50.72, Immediate Notification Requirements for Operating Nuclear Power Reactors.
  6. H. Ashar and G. Bagchi, Assessment of Inservice Condition of Safety-Related Nuclear Plant Structures, U.S. Nuclear Regulatory Commission, NUREG-1522, Washington, D.C., June 1995.
  7. U.S. Nuclear Regulatory Commission, 10 CFR Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants.
  8. U.S. Nuclear Regulatory Commission, 10 CFR Part 51, Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions.