Community Research and Development Information Service - CORDIS

Abstract

A multi-fluid version of the nuclear reactor code RELAP5/MOD1 has been developed in order to study two-phase flow transients in thermal-hydraulic systems with working fluids other than water. Although not a true multi-component mixture code, a modular approach has been adopted to permit a number of different working fluids to be specified within the different circuits. The constitutive relationships have been generalised to make them applicable to a wide variety of fluids. In particular, the correlations for heat and mass transfer, as well as the parameters used for determining flow patterns and the calculation of interface drag, have been re-formulated to remain consistent with the specified working fluid. Possible fields of application include blowdown/venting of storage tanks, vessel and piping systems, transients in thermal-hydraulic networks caused by component failures or malfunctions, and operational transients in systems containing heat exchangers.

Additional information

Authors: FRANCHELLO G, JRC Ispra (IT);STÄDTKE H, JRC Ispra (IT);WORTH B, JRC Ispra (IT)
Bibliographic Reference: EUR 15141 EN (1993) 59 pp., FS, free of charge
Availability: Available from Joint Research Centre, Publication Department, I-21020 Ispra (Va.) (IT)
Record Number: 199511408 / Last updated on: 1995-10-31
Category: PUBLICATION
Original language: en
Available languages: en