FIELD: nuclear industry.
SUBSTANCE: invention relates to a method for monitoring density of the neutron flux, and can be used in control systems, monitoring and protection of nuclear installations. Ionization pulse-current fission chamber registers a neutron flux, discriminates pulse signal in amplitude, and forms formalized pulses. Then formalized pulses are converted into a code proportional to the number of pulses from the discriminator, and that number is corrected according to the algorithm for calculating count rate of pulse signal of the fission chamber according to the corrective characteristic of pulses miscalculations, after which a signal is generated proportional to count rate of pulse signal of the fission chamber. Corrective characteristic is dependence of count rate of pulse signal from the fission chamber on the number of pulses from the discriminator at different values of the measuring channel load.
EFFECT: improved accuracy of monitoring neutron flux density in a wide range of measurements.
1 cl, 2 dwg
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