Progress in understanding of direct containment heating phenomena in pressurized light water reactors

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Progress is described in development of a mechanistic understanding of direct containment heating phemonena arising during high-pressure melt ejection accidents in pressurized water reactor systems. The experimental data base is discussed which forms the basis for current assessments of containment pressure response using current lumped-parameter containment analysis methods. The deficiencies in available methods and supporting data base required to describe major phenomena occurring in the reactor cavity, intermediate subcompartments and containment dome are highlighted. Code calculation results presented in the literature are cited which demonstrate that the progress in understanding of DCH phenomena has also resulted in current predictions of … continued below

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12 pages

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Ginsberg, T. & Tutu, N.K. January 1, 1988.

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Description

Progress is described in development of a mechanistic understanding of direct containment heating phemonena arising during high-pressure melt ejection accidents in pressurized water reactor systems. The experimental data base is discussed which forms the basis for current assessments of containment pressure response using current lumped-parameter containment analysis methods. The deficiencies in available methods and supporting data base required to describe major phenomena occurring in the reactor cavity, intermediate subcompartments and containment dome are highlighted. Code calculation results presented in the literature are cited which demonstrate that the progress in understanding of DCH phenomena has also resulted in current predictions of containment pressure loadings which are significantly lower than are predicted by idealized, thermodynamic equilibrium calculations. Current methods are, nonetheless, still predicting containment-threatening loadings for large participating melt masses under high-pressure ejection conditions. Recommendations for future research are discussed. 36 refs., 5 figs., 1 tab.

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12 pages

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NTIS, PC A03/MF A01 - OSTI; 1.

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  • 3. international topical meeting on nuclear power plant thermal hydraulics and operations, Seoul, Korea, 14 Nov 1988

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  • Other: DE89001102
  • Report No.: BNL-NUREG-41751
  • Report No.: CONF-881115-4
  • Grant Number: AC02-76CH00016
  • Office of Scientific & Technical Information Report Number: 6650981
  • Archival Resource Key: ark:/67531/metadc1194109

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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, 1988

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  • July 3, 2018, 8:14 a.m.

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  • June 25, 2019, 1:15 p.m.

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Ginsberg, T. & Tutu, N.K. Progress in understanding of direct containment heating phenomena in pressurized light water reactors, article, January 1, 1988; Upton, New York. (https://digital.library.unt.edu/ark:/67531/metadc1194109/: accessed May 27, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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