Analyses of postulated ALMR containment and steam generator building accidents using the CONTAIN-LMR code

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The development of liquid metal reactor concepts with passive safety characteristics is in progress at the General Electric Company under contract to the US Department of Energy. To assess the performance of these systems under postulated severe accident conditions analyses of containment accidents relating to the breach of the primary coolant boundary of the Department of Energy Advanced Liquid Metal Reactor were completed by Westinghouse Hanford Company for the plant designer General Electric. A series of three accident cases were selected by General Electric for characterizing the containment responding to a hypothetical core disruptive accident. In addition, the Advanced Liquid … continued below

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11 p.

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Chiao, T.; Wood, S. A.; Shen, P. K.; Baker, R. B. & Gluekler, E. L. January 1, 1994.

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  • Westinghouse Hanford Company
    Publisher Info: Westinghouse Hanford Co., Richland, WA (United States)
    Place of Publication: Richland, Washington

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Description

The development of liquid metal reactor concepts with passive safety characteristics is in progress at the General Electric Company under contract to the US Department of Energy. To assess the performance of these systems under postulated severe accident conditions analyses of containment accidents relating to the breach of the primary coolant boundary of the Department of Energy Advanced Liquid Metal Reactor were completed by Westinghouse Hanford Company for the plant designer General Electric. A series of three accident cases were selected by General Electric for characterizing the containment responding to a hypothetical core disruptive accident. In addition, the Advanced Liquid Metal Reactor Steam Generator Building was also analyzed to demonstrate the acceptability of the Steam Generator Building sodium fire protection strategy related to a design-basis leak.

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11 p.

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INIS; OSTI as DE94005490; Paper copy available at OSTI: phone, 865-576-8401, or email, reports@adonis.osti.gov

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  • International topical meeting on the safety of advanced reactors,Pittsburgh, PA (United States),18-20 Apr 1994

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  • Other: DE94005490
  • Report No.: WHC-SA--2121
  • Report No.: CONF-940402--3
  • Grant Number: AC06-87RL10930
  • Office of Scientific & Technical Information Report Number: 10117067
  • Archival Resource Key: ark:/67531/metadc1273977

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Office of Scientific & Technical Information Technical Reports

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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, 1994

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  • Oct. 12, 2018, 6:44 a.m.

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  • Nov. 13, 2018, 2:28 p.m.

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Chiao, T.; Wood, S. A.; Shen, P. K.; Baker, R. B. & Gluekler, E. L. Analyses of postulated ALMR containment and steam generator building accidents using the CONTAIN-LMR code, article, January 1, 1994; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1273977/: accessed May 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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