Integrated analysis of DCH in Surry

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An evaluation of the key elements affecting Direct Containment Heating (DCH) was performed for the Surry plant. This involved determining the dominant high pressure core damage sequences, the probability of proceeding to vessel breach at high pressure, the DCH loads, and the containment strength. Each of these factors was evaluated separately, and then the results were combined to give the overall threat from DCH. The maximum containment failure probability by DCH for Surry is 10{sup {minus}3} when considering four base DCH scenarios and using the two-cell equilibrium (TCE) model. However, higher contamination failure probabilities are estimated in sensitivity cases. When ... continued below

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19 p.

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Dingman, S. E.; Harper, F. T.; Pilch, M. M. & Washington, K. E. December 31, 1993.

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  • Sandia National Laboratories
    Publisher Info: Sandia National Labs., Albuquerque, NM (United States)
    Place of Publication: Albuquerque, New Mexico

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Description

An evaluation of the key elements affecting Direct Containment Heating (DCH) was performed for the Surry plant. This involved determining the dominant high pressure core damage sequences, the probability of proceeding to vessel breach at high pressure, the DCH loads, and the containment strength. Each of these factors was evaluated separately, and then the results were combined to give the overall threat from DCH. The maximum containment failure probability by DCH for Surry is 10{sup {minus}3} when considering four base DCH scenarios and using the two-cell equilibrium (TCE) model. However, higher contamination failure probabilities are estimated in sensitivity cases. When the depressurization and containment loads aspects are combined, the containment failure probability (conditional on station blackout sequence) is less than 19{sup {minus}2}. CONTAIN calculations were performed to provide insights regarding DCH phenomenological uncertainties and potential conservatisms in the TCE model. The CONTAIN calculations indicated that the TCE calculations were conservative for Surry and that the dominant factors were neglect of heat transfer to surroundings and complete combustion of hydrogen on DCH time scales.

Physical Description

19 p.

Notes

INIS; OSTI as DE94008870; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov

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  • 21. water reactor safety information meeting,Bethesda, MD (United States),25-27 Oct 1993

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  • Other: DE94008870
  • Report No.: SAND--93-2261C
  • Report No.: CONF-931079--22
  • Grant Number: AC04-94AL85000
  • Office of Scientific & Technical Information Report Number: 10135967
  • Archival Resource Key: ark:/67531/metadc1316120

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • December 31, 1993

Added to The UNT Digital Library

  • Nov. 3, 2018, 11:47 a.m.

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  • April 2, 2019, 4:09 p.m.

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Dingman, S. E.; Harper, F. T.; Pilch, M. M. & Washington, K. E. Integrated analysis of DCH in Surry, article, December 31, 1993; Albuquerque, New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc1316120/: accessed April 24, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.