Some Aspects of Safety Characteristics of High Temperature Reactors

Abstract

A numerical model for the description of water and air ingress accidents in the primary loop of the high temperature reactors is presented in this paper. The code TINTE developed in Institut fuer Reaktorentwicklung of Forschungszentrum Juelich, FRG (now Institut fuer Sicherheitsforschung und Reaktortechnik) is further improved and can be used for such an accident analysis. The thermo fluid dynamics by different heat transport characteristics and the chemical processes between water, air and graphite on the basis of new experimental results are taken into consideration. The influence of the composition of cooling gas and graphite corrosion on the nuclear characteristics is also included. The developed computer code TINTE-C is tested on a fictious example of a water ingress accident at the AVR reactor.