Published 1990
| Version v1
Report
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The MELTSPREAD-1 computer code for the analysis of transient spreading in containments
Description
A one-dimensional, multicell, Eulerian finite difference computer code (MELTSPREAD-1) has been developed to provide an improved prediction of the gravity driven spreading and thermal interactions of molten corium flowing over a concrete or steel surface. In this paper, the modeling incorporated into the code is described and the spreading models are benchmarked against a simple ''dam break'' problem as well as water simulant spreading data obtained in a scaled apparatus of the Mk I containment. Results are also presented for a scoping calculation of the spreading behavior and shell thermal response in the full scale Mk I system following vessel meltthrough. 24 refs., 15 figs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A02/MF A01 as DE90017695; OSTI; INIS; US Govt. Printing Office Dep.Files
22069494.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- CONF-901101--30
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-15 Nov 1990.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22069494
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; C CODES; COMPUTER CALCULATIONS; CONTAINMENT; CORIUM; FLOW MODELS; FLUID FLOW; HEAT TRANSFER; HYDRAULICS; M CODES; MATHEMATICAL MODELS; MELTDOWN; REACTOR COMPONENTS; REACTOR SAFETY; THERMAL ANALYSIS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38; Contract RP 3047-2