Published 1990 | Version v1
Book

The meltspread-1 computer code for the analysis of transient spreading in containments

  • 1. Argonne National Lab., Evanston, IL (United States)

Description

This paper reports on a one-dimensional, multicell, Eulerian finite difference computer code (MELTSPREAD-1) that 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. The 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

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL (United States)
ISBN
0-89448-156-8
Imprint Title
ANS sixth proceedings of the nuclear thermal hydraulics
Imprint Pagination
412 p.
Journal Page Range
p. 21-34.

Conference

Title
American Nuclear Society (ANS) winter meeting.
Dates
11-16 Nov 1990.
Place
Washington, DC (United States).

Optional Information

Secondary number(s)
CONF-901101--.