ASSESSMENT OF TWO-PHASE CRITICAL FLOW MODELS OF RELAN5/MOD2 AND CATHARE CODE

1 Boure JA. The Critical Flow Phenomenon With Refence to Two-Phase Plow and Nuclear Reactor Systems. The Winter Annual Meeting of the ASME, 1977, 1: 195． 2 Ransom VH. RELAP5/MOD2 Code Manual, 1985, 1: 8． 3 Eguipe Mixte EDF-CEA-FRAMATOME, Modele D'ecoulement Diphadique Monodimensionnel en Regime Transitoire, D213-1 D213-1, 1984． 4 Shepherd IM. Modelling the Critical Flow in LOBI Small Break Experiments. Proceedings of the International ENS/ANS Conference on Thermal Reactor Safety, Avignon, France 1988, 10． 5 Jeandey C, Gros L, Bourgine R, et al. Auto-Vaporisation D'ecoulements Eau/Vapeur. CEA Rapport T·T·NO 163, Juillet, 1981． 6 Chataing T, Clement P. BETHSY Preliminary Data Comparison Report for International Standard Problem 27, 2"Cold Leg Break Without HPSI and With Delayed Ultimate Procedure. Centre D'etudes Nucleairesde GRENOBLE, 1991．