• SAFETY ANALYSIS OF POWER EXCURSION ACCIDENTS FOR TRAINING AND RESEARCH REACTORS USING DIFFERENT THERMAL-HYDRAULIC MODELS

Abstract

It is true that most power reactors have a code system to analyze the consequences of reactivity transients but is not true for a number of training and research reactors as to the training and research reactor of Budapest University of Technology (BME). The authority's inspection is looming and new programs had to be elaborated to meet the authority requirements. In this sense two different 3D space-time dependent models with thermal-hydraulics feedback has been introduced and compared together and with point-kinetic model for this purpose. The two integrated 3D neutronic/thermal-hydraulic codes POWEX-K/MI and POWEX-K/SV together with point kinetic REMEG code has been tested and compared to analyze power excursion accidents initiated by ramp reactivity 1.2$. A comparison between two models has been given and the physical and mathematical features of both models have been investigated. The results show that the fuel parameters are maintained below specified limits during the accident so that fuel failure and release of radioactivity will not occur.