The code crest to simulate criticality accident power excursion in fuel solution

Nuclear power excursions in solution fuel systems are characterized by the negative reactivity feedback due to radiolytic gas void and in some cases, the appearance of power oscillations. The simulation model of the fission power and solution temperature transients during the entire periods from the early prompt critical stage, the subsequent power oscillation stage due to radiolytic gas formation, to the slow power decrease stage has been developed. The code is based on the point reactor kinetics and the reactivity feedback coupled with the single region thermal and hydraulic calculation, which is the non-time consuming simulation by the personal-computer. The model reproduces the experiments well