Validation of the CRITEX code

The CRITEX code has been developed to simulate criticality transients in fissile liquids. Validation of the code has been made by comparison with experimental results from the SILENE and CRAC reactors. The main methods of reactivity feedback have been identified and programmed into the code. The values of neutron lifetime, k infinity and neutronic temperature effect have been found from the use of the WIMS suite of codes. A parameter has been defined which controls the rate at which radiolytic gas is released from solution. Comparisons of CRITEX and experimental results have been made for a wide range of transient speed. (Author)