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Code validation with EBR-II test data.

Author: Hill, D.J.; Chang, L.K.; Feldman, E.E.; Herzog, J.P.; Dean, E.M.; Mohr, D.; Planchon, H.P.; Argonne National Lab.; United States. Department of Energy.; United States. Department of Energy. Office of Scientific and Technical Information.
Publisher: Washington, D.C. : United States. Dept. of Energy ; Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1992.
Edition/Format:   eBook : Document : Conference publication : National government publication : EnglishView all editions and formats
Database:WorldCat
Summary:
An extensive system of computer codes is used at Argonne National Laboratory to analyze whole-plant transient behavior of the Experimental Breeder Reactor 2. Three of these codes, NATDEMO/HOTCHAN, SASSYS, and DSNP have been validated with data from reactor transient tests. The validated codes are the foundation of safety analyses and pretest predictions for the continuing design improvements and experimental  Read more...
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Material Type: Conference publication, Document, Government publication, National government publication, Internet resource
Document Type: Internet Resource, Computer File
All Authors / Contributors: Hill, D.J.; Chang, L.K.; Feldman, E.E.; Herzog, J.P.; Dean, E.M.; Mohr, D.; Planchon, H.P.; Argonne National Lab.; United States. Department of Energy.; United States. Department of Energy. Office of Scientific and Technical Information.
OCLC Number: 727283123
Notes: Published through the Information Bridge: DOE Scientific and Technical Information.
01/01/1992.
"Anl/cp-74826."
"Conf-920804--18."
"DE92016604."
American Society of Mechanical Engineers national heat transfer conference and exposition, San Diego, CA (United States), 9-12 Aug 1992.
Hill, D.J.; Chang, L.K.; Feldman, E.E.; Herzog, J.P.; Dean, E.M.; Mohr, D.; Planchon, H.P.
Description: pages (27 pages) : digital, PDF file

Abstract:

An extensive system of computer codes is used at Argonne National Laboratory to analyze whole-plant transient behavior of the Experimental Breeder Reactor 2. Three of these codes, NATDEMO/HOTCHAN, SASSYS, and DSNP have been validated with data from reactor transient tests. The validated codes are the foundation of safety analyses and pretest predictions for the continuing design improvements and experimental programs in EBR-II, and are also valuable tools for the analysis of innovative reactor designs.

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