Published 1986 | Version v1
Report Restricted

MELPROG/TRAC: update and applications

Description

The first complete, coupled, and mechanistic analysis of a core meltdown sequence has been made with MELPROG-PWR/MOD1 and MELPROG/TRAC. The sequence analyzed was a station blackout accident for the Surry plant. Through vessel failure, all important aspects of the meltdown sequence were calculated. This version of MELPROG permits a full two-dimensional treatment of the in-vessel phenomena. Natural circulation can thus be modeled. Comparison to one-dimensional MELPROG and MARCH calculations shows that natural circulation reduces the rate of core heating, but increases the rate of heating of upper plenum structures and primary piping. This increased heating can inhibit fission product deposition and may lead to an early failure of the primary system. Because of uncertainty, sensitivity studies were performed to assess the relative importance of modeling assumptions. Changes in the modeling of the initial fuel rod melting and relocation were found to vary the hydrogen source by a factor of 2 and alter the timing of key events. These results imply that accurate and mechanistic modeling is important for severe accident sequence analysis

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE87001984.

Files

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Additional details

Publishing Information

Imprint Pagination
25 p.
Report number
LA-UR--86-3691

Conference

Title
14. water reactor safety information meeting.
Dates
27-31 Oct 1986.
Place
Gaithersburg, MD (USA).

Optional Information

Notes
Portions of this document are illegible in microfiche products.
Secondary number(s)
CONF-8610135--31.