Description of Physics Data for CATHENA Safety Analysis of the MAPLE-X10 Reactor

Abstract

The transient safety analysis of the MAPLE-X10 Reactor has been performed using the thermalhydraulics code CATHENA together with either a point reactor kinetics model within CATHENA or a separate two-dimensional kinetics and thermalhydraulics calculation within the code TANK. This paper summarizes all the sources of reactor physics data supplied to CATHENA for the transient simulations. The physics methods used to obtain them and the underlying assumptions are discussed.