Community Research and Development Information Service - CORDIS

Abstract

The thermohydraulic reactor safety code TRAC PF1 has been implemented on the JRC Ispra computer. Code assessment work so far has concentrated on one component with simple tests the effect of modifying correlations, nodalization and numerics can be assessed more clearly. Some illustrative results are presented for a boildown/refill transient. A numerical test is also shown where several methods of coupling the rod to the fluid are compared. The differences between the solutions in each case justify the continuation of this type of single component analysis.

Additional information

Authors: DIFFIELD J, JRC ISPRA ESTAB.;SHEPHERD I, JRC ISPRA ESTAB.;RUEL F, JRC ISPRA ESTAB.;WUERTZ J JRC ISPRA ESTAB., JRC ISPRA ESTAB.
Bibliographic Reference: TASK GROUP ON STATUS AND ASSESSMENT OF CODES FOR TRANSIENTS AND ECCS, PARIS (FRANCE), JUNE 23-24, 1983 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 31165 ORA
Availability: Can be ordered online
Record Number: 1989122028100 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en