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Title Performance testing of thermal analysis codes for nuclear fuel casks
Creator/Author Sanchez, L.C. (ed.)
Publication Date1987 Jan 01
OSTI IdentifierOSTI ID: 7186209; Legacy ID: DE87005215
Report Number(s)SAND-84-1854; TTC-0509
DOE Contract NumberAC04-76DP00789
Other Number(s)Other: ON: DE87005215
Resource TypeTechnical Report
Resource RelationOther Information: Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted
Research OrgSandia National Labs., Albuquerque, NM (USA)
Subject11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; HEAT TRANSFER; COMPUTER CODES; SPENT FUEL CASKS; BENCHMARKS; PERFORMANCE TESTING; CASKS; CONTAINERS; ENERGY TRANSFER; TESTING
Description/AbstractIn 1982 Sandia National Laboratories held the First Industry/Government Joint Thermal and Structural Codes Information Exchange and presented the initial stages of an investigation of thermal analysis computer codes for use in the design of nuclear fuel shipping casks. The objective of the investigation was to (1) document publicly available computer codes, (2) assess code capabilities as determined from their user's manuals, and (3) assess code performance on cask-like model problems. Computer codes are required to handle the thermal phenomena of conduction, convection and radiation. Several of the available thermal computer codes were tested on a set of model problems to assess performance on cask-like problems. Solutions obtained with the computer codes for steady-state thermal analysis were in good agreement and the solutions for transient thermal analysis differed slightly among the computer codes due to modeling differences.
Country of PublicationUnited States
LanguageEnglish
FormatMedium: X; Size: Pages: 62
AvailabilityNTIS, PC A04/MF A01; 1.
System Entry Date2008 Feb 12

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