To accurately understand the continuous positional distribution of neutron fluence.
There is provided a coating which is, e.g., in a fuel processing facility relating to atomic power, applied to: the road surface of roads in the facility and facility periphery; the surface of exterior materials set on the building surface of the facility, the surface of wall paper covering the wall surface of the facility and the external wall of the facility; and the surface and the like of machineries set in the facility. The coating contains a material having an activation cross section or a neutron interaction cross section larger than a predetermined value with a predetermined weight concentration, and an analytical object material can produce radioactive materials by activation with neutron radiation or nuclear fission with neutron radiation. The predetermined weight concentration of the analytical objective material is set based on the distance from a neutron generation source to a coated part, the radioactivity of a radioactive material, and the predetermined detective efficiency of radiation radiated from the radioactive material.
Noriaki Uchino
Nobuyuki Kimura