Experience in Development of a Research Reactor Simulator

Nuclear safety not only depends on the reliability and safety of the structures, systems, and components (SSCs) but also largely depends on human factors and interaction of operators with machines. Simulators greatly support in the training and transfer of knowledge to the plant operators. This paper shares an experience in indigenous development of full scope, non-replica simulator for a more than 30 years old, 100 MW research reactor at BARC Trombay. The simulator was so designed that over and above training of the plant personnel, it will be used for safety studies in the area of reactor physics and thermal hydraulics. The interface was designed to support the interaction of the operators with the simulator through virtual panels supported by touch screens with high-fidelity graphic displays. Important postulated initiating events (PIEs) like loss of offsite power, loss of coolant accident, loss of regulation incident, etc. have been modeled. This information will provide an insight to verify and validate the plant emergency operating procedures (EOPs). The simulator will also be used for the development of human factor models as well as the design of future visual display unit (VDU)-based control rooms. This will also enable the operators to align themselves from the traditional panel-based human–machine interface (HMI) to personal computers.