Modelling of critical functions of nuclear reactors using Fild Programmable Gate Array

This paper proposes the development of a method using FPGA for critical security functions of a nuclear reactor. It was implemented two critical safety functions in VHDL, which is a way to describe, through a program, the behavior of a circuit or digital component. Two critical security functions, FCS Core Cooling, responsible for cooling the reactor core in the charts of the plant and also in the event of accidents involving loss of coolant and FCS Heat Transfer, responsible for cooling the reactor core in the event an accident with loss of coolant were implemented. In this Dissertation it was chosen the use of FPGA, because - due to the effects of aging, obsolescence issues, environmental degradation and mechanical failures - nuclear power plants need to replace their older systems by new ones based on digital technology. The technologies obtained using a system described in hardware language can be implemented in a programmable device, having the advantage of changing the code at any time. (author)