Thermohydraulic design model of NPP Krsko reactor core with computer code COBRA-III-C

Using the computer code COBRA-III-C an analytical design model was developed for the evaluation of the thermal-hydraulic performance of the NPP Krsko nuclear reactor core. depending on the available publications and code capability we followed the Westinghouse design methods with codes THNIC-I and THNIC-IV. The minimum DNBR in the core was analyzed and impact of mixed KWU-WES core was evaluated. The results are in excellent agreement with vendor's results despite the fact that many vendor design methods and values were not known. With the presented model the influence of any changes on thermal hydraulic parameters in core could further be analyzed. (author)