MELCOR 1.8.2 assessment: Surry PWR TMLB` (with a DCH study)

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Description

MELCOR is a fully integrated, engineering-level computer code, being developed at Sandia National Laboratories for the USNRC. This code models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRs. As part of an ongoing assessment program, the MELCOR computer code has been used to analyze a station blackout transient in Surry, a three-loop Westinghouse PWR. Basecase results obtained with MELCOR 1.8.2 are presented, and compared to earlier results for the same transient calculated using MELCOR 1.8.1. The effects of new models added in MELCOR 1.8.2 (in particular, hydrodynamic interfacial momentum exchange, core debris ... continued below

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319 p.

Creation Information

Kmetyk, L.N.; Cole, R.K. Jr.; Smith, R.C.; Summers, R.M. & Thompson, S.L. February 1, 1994.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 18 times . More information about this report can be viewed below.

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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

MELCOR is a fully integrated, engineering-level computer code, being developed at Sandia National Laboratories for the USNRC. This code models the entire spectrum of severe accident phenomena in a unified framework for both BWRs and PWRs. As part of an ongoing assessment program, the MELCOR computer code has been used to analyze a station blackout transient in Surry, a three-loop Westinghouse PWR. Basecase results obtained with MELCOR 1.8.2 are presented, and compared to earlier results for the same transient calculated using MELCOR 1.8.1. The effects of new models added in MELCOR 1.8.2 (in particular, hydrodynamic interfacial momentum exchange, core debris radial relocation and core material eutectics, CORSOR-Booth fission product release, high-pressure melt ejection and direct containment heating) are investigated individually in sensitivity studies. The progress in reducing numeric effects in MELCOR 1.8.2, compared to MELCOR 1.8.1, is evaluated in both machine-dependency and time-step studies; some remaining sources of numeric dependencies (valve cycling, material relocation and hydrogen burn) are identified.

Physical Description

319 p.

Notes

INIS; OSTI as DE94008819

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  • Other Information: PBD: Feb 1994

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  • Other: DE94008819
  • Report No.: SAND--93-1899
  • Grant Number: AC04-94AL85000
  • DOI: 10.2172/142535 | External Link
  • Office of Scientific & Technical Information Report Number: 142535
  • Archival Resource Key: ark:/67531/metadc623213

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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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  • February 1, 1994

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 13, 2016, 2:57 p.m.

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Kmetyk, L.N.; Cole, R.K. Jr.; Smith, R.C.; Summers, R.M. & Thompson, S.L. MELCOR 1.8.2 assessment: Surry PWR TMLB` (with a DCH study), report, February 1, 1994; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc623213/: accessed December 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.