Development of a New Clearance Monitor for Exemption of NPP Radioactive Wastes and its Performance Test - 17200
In nuclear power plants, it is common practice to clear radioactive wastes for free release by using clearance monitor with plastic scintillation detectors so as to reduce disposal costs. These monitors are possible in part thanks to the excellent detection levels achievable with high energy and high yield photons emitted from contaminants such as Cs-137 and Co-60. However, it is difficult for the monitors to separate Naturally Occurring Radioactive Materials (NORM) from the radioactive wastes because the plastic scintillation detectors have poor resolution compared to NaI or HPGe detectors. KHNP has developed a new clearance monitor for determining whether or not the radioactivity level of metal scraps satisfies regulatory criteria. The monitor is composed of 12 large area plastic scintillation detectors and 3 NaI scintillation detectors. The measuring chamber is surrounded by a 5 cm-thick lead shield with chamber dimensions of 1.5 m x 1.0 m x 1.0 m. Its algorithm has a function of measuring total gamma activity while analyzing gamma nuclides and identifying 27 hotspots in radioactive wastes. The detection limit of this system, according to the MCNP simulation, was determined to be about 45 Bq for Co-60 and 78 Bq for Cs-137 with the condition of an empty chamber and measuring time of 1 minute. We evaluated the self - shielding effect of waste for background correction factor and waste height (volume in the chamber) correction factor. We also tested its MDA, location determination of hot-spots, temperature compensation function and convenience of operation. In the future, we will plan to install it at a nuclear site for more tests including evaluating its durability. (authors)