Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Failure modes analysis for BWR Mark-2 in-pedestal dry-well drain pipes

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:5763668
 [1];  [2]
  1. Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)
  2. Rensselaer Polytechnic Inst., Troy, NY (United States)
Several boiling water reactor (BWR) Mark-2 containment dry wells include drain pipes that penetrate the concrete pedestal floor and lead into the wet-well region. For example, these pipes are installed in the Limerick, LaSalle, and WNP-2 BWR plants. During severe-accident melt progression events, these penetrations might provide pathways for the rapid relocation of molten corium out of the in-pedestal region, and the passive suppression capability of the containment may be lost. Early pressure suppression pool bypass could also lead to detrimental effects if containment venting were employed. Analyses of this issue were conducted by the US Nuclear Regulatory Commission's BWR Mark-2 and -3 parametrics program at Oak Ridge National Laboratory. The results of these analyses are presented in this paper.
OSTI ID:
5763668
Report Number(s):
CONF-910603--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
Country of Publication:
United States
Language:
English