Measurement of reactor power by solid state nuclear track detector

The paper describes a method for reactor power measurement by Solid State Nuclear Track Detector (SSNTD) which includes direct measurement of fission rate in fuel element in zero power reactor and calculation of reactor power from the fission rate and the energy generated in each fission. At the same time thermal neutron flux density at certain points is measured and then thermal neutron flux density of unite power is given. Thus, power can be obtained by measuring the thermal neutron flux density at this point. Comparing with activation method, the method has some advantages, for example reducing the correction about the spectrum measurement, the irradiation neutron flux density is lower and the irradiation time is shorter