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A Feasibility Study on Aluminum Nitride Pieces for an Application to the Nuclear Power Plant Flux Detector

The sensitivity of a solid-state flux detector is studied using a 3mm× 3mm× 0.635mm size aluminum nitride piece. We describe the results of the gamma measurements in the high flux Co 60 irradiation facility and the neutron measurements in a beam port of the HANARO research reactor where the gamma flux is about 1% of the neutron. The measured results are compared with the calculated results based on the MCNP4B and EGS4 code. The current generated by the neutron flux is calculated by using the MCNP4B code and the current generated by the gamma flux is computed by using the EGS4 code. The calculation results for the expected current in the full power PWR nuclear power plants are included.