[en] Currently, the use of digital computers in energy producing systems has been limited to data acquisition functions. These computers have greatly reduced human involvement in the moment to moment decision process and the crisis decision process, thereby improving the safety of the dynamic energy producing systems. However, in addition to data acquisition, control of energy producing systems also includes data comparison, decision making, and control actions. The majority of the later functions are accomplished through the use of analog computers in a distributed configuration. The lack of cooperation and hence, inefficiency in distributed control, and the extent of human interaction in critical phases of control have provided the incentive to improve the later three functions of energy systems control. Properly applied, centralized control by digital computers can increase efficiency by making the system react as a single unit and by implementing efficient power changes to match demand. Additionally, safety will be improved by further limiting human involvement to action only in the case of a failure of the centralized control system. This paper presents a hardware and software design for the centralized control of a research nuclear reactor by a digital computer. Current nuclear reactor control philosophies which include redundancy, inherent safety in failure, and conservative yet operational scram initiation were used as the bases of the design. The control philosophies were applied to the power monitoring system, the fuel temperature monitoring system, the area radiation monitoring system, and the overall system interaction. Unlike the single function analog computers that are currently used to control research and commercial reactors, this system will be driven by a multifunction digital computer. Specifically, the system will perform control rod movements to conform with operator requests, automatically log the required physical parameters during reactor operation, perform the required system tests, and monitor facility safety and security. Reactor power control is based on signals received from ion chambers located near the reactor core. Absorber rod movements are made to control the rate of power increase or decrease during power changes and to control the power level during steady state operation. During operation, physical parameters such as power output, fuel temperature, laboratory radiation levels, control rod levels, and coolant pH, conductivity, and level are monitored and logged continually. Most of these parameters also serve as scram trips when they exceed preset values. Additionally, the system incorporates rudimentary artificial intelligence. Changes in core materials and structure will change reactor response characteristics. The change in system performance is evaluated during periodic system tests where the computer records data such as integral and differential control rod worths and thermal power output. This data is used to modify the data acquisition functions and the system response in a manner similar to biological learning experiences. (author)