COMPUTERIZED SAFETY SYSTEM FOR RESEARCH REACTORS

摘要

The invention relates to an automatic system for measuring and monitoring the operation parameters of a research reactor under safety conditions or when the reactor operation is suspended. According to the invention, the system comprises three channels (CN1, CN2 and CN3) for measuring the neutron power, each of them receiving signals from one of some fission chambers (CF2, CF3 and CF4) placed in the close vicinity of a reactor core, two channels (Clog and Clin), a logarithmic one and a linear one, respectively, being provided for measuring the neutron power, said channels using a signal coming from a fission chamber (CF1) placed in the closed vicinity of the reactor core and passing through a preamplifier (PreA) located near the said last fission chamber (CF1), while the temperature of some fuel elements is measured through three measuring channels (TpA, TpB and TpC) receiving signals from some thermocouples (Te1, Te2, Te3, Te4, Te5 and Te6) placed inside the fuel elements, by means of a switch.