Containment performance for the core melt accidents in BWRs with Mark I and Mark II containments

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Most previous risk assessment studies have assumed catastrophic failure of containments for severe accidents which are predicted to exceed the containment yield stress. This investigation analyzes the progression of a severe accident in order to develop realistic containment temperature and pressure loading, utilizes models for containment leakage estimates for the various loading histories, and assesses the expected failure modes and timing of releases for core melt accidents in Boiling Water Reactors (BWRs) with Mark I and Mark II containments. The results of the investigation indicate that leakage through the seal on the drywell head may be sufficient to prevent catastrophic ... continued below

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Pages: 13

Creation Information

Perkins, K.R.; Yang, J.W.; Greene, G.A.; Pratt, W.T. & Hofmayer, C. January 1, 1985.

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Description

Most previous risk assessment studies have assumed catastrophic failure of containments for severe accidents which are predicted to exceed the containment yield stress. This investigation analyzes the progression of a severe accident in order to develop realistic containment temperature and pressure loading, utilizes models for containment leakage estimates for the various loading histories, and assesses the expected failure modes and timing of releases for core melt accidents in Boiling Water Reactors (BWRs) with Mark I and Mark II containments. The results of the investigation indicate that leakage through the seal on the drywell head may be sufficient to prevent catastrophic failure of the containments for a wide range of hypothetical core melt scenarios. In addition, the investigation has indicated the potential for a previously inidentified failure mode (containment liner meltthrough) for Mark I containments in which a large fraction of the core is released from the vessel in a molten state. 14 refs.

Physical Description

Pages: 13

Notes

NTIS, PC A02/MF A01 - GPO.

Source

  • International ANS/ENS topical meeting on probabilistic safety methods and applications, San Francisco, CA, USA, 24 Feb 1985

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  • Other: TI86007127
  • Report No.: BNL-NUREG-37676
  • Report No.: CONF-850206-35
  • Grant Number: AC02-76CH00016
  • Office of Scientific & Technical Information Report Number: 6250306
  • Archival Resource Key: ark:/67531/metadc1113302

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • January 1, 1985

Added to The UNT Digital Library

  • Feb. 22, 2018, 7:45 p.m.

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  • March 22, 2018, 4:34 p.m.

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Perkins, K.R.; Yang, J.W.; Greene, G.A.; Pratt, W.T. & Hofmayer, C. Containment performance for the core melt accidents in BWRs with Mark I and Mark II containments, article, January 1, 1985; United States. (digital.library.unt.edu/ark:/67531/metadc1113302/: accessed April 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.