Measurement of neutronic safety parameters of the 3 MW TRIGA Mark-II research reactor

Abstract

Measurement of neutronic safety parameters of the nuclear reactor is very important for reactor safety, efficient operation and experimental research. In this study, some neutronic safety parameters such as control rod worth, core excess reactivity, loss of reactivity with power increases, power defect, reactivity coefficients, cooling effect on fuel temperature and xenon poisoning were measured of the 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC). All of these safety parameters have significant effect on the reactor control system. Many of the reactor parameters which determine the reactivity of reactor are dependent on the temperature of the fuel, moderator and coolant. The TRIGA fuel elements have been designed to provide a significant prompt negative temperature coefficient of reactivity that allows safe reactor operation. The neutronic safety parameters were measured with digital instrumentation & control (I&C) system of the 3 MW TRIGA research reactor. The experimental results of neutronic parameters were found within the safety limit as mentioned in the Safety Analysis Report (SAR) of the BAEC 3 MW TRIGA research reactor. The present study will contribute to analyze the behavior of neutronic safety parameters that occur in the reactor core and to provide an experimental database for validation and improvement of the models of the reactor.