The amount of radioactive waste generated during decommissioning directly affects the disposal cost of waste. Most of the radioactive waste generated is a concrete waste. Therefore reducing the amount of concrete waste can ensure the economic feasibility of the decommissioning project. The activated concrete in a concrete waste can reduce waste only by physical cutting. Therefore it is most important to accurately identify and categorize radionuclides, radioactivity levels, and radioactivity distribution. In the case of radioactive concrete, radiological characteristics are generally evaluated by laboratory analysis after sampling. However it is difficult to apply to all facilities (accelerator & NPP, etc.) because it is a destructive method. Therefore it is necessary to secure verified in-situ measurement technology that can be applied to operational monitoring or decommissioning plans. In this study, the applicability of cyclotron facilities was evaluated based on the evaluation algorithm derived from the Peak to Compton (PTC) method of in-situ measurement technology. And the reliability of the PTC method was verified through qualitative analysis and quantitative analysis. In the case of qualitative analysis, the analysis results of KAERI which has core technology are compared. To this end SAEAN and KAERI conducted field application tests on the front concrete shielding wall of the cyclotron facility at the same time. After removing the background spectrum from the measured spectrum the PTC method was applied to calculate the Q-value for the counting rate in the peak area per counting rate in the Compton continuum area was calculated. As a result the Q-values of SAE-AN and KAERI were 0.52 and 0.24 respectively, and the result of deriving activation distribution(β) by substituting this for the β-Q correlation equation was found that 14.78 and 12.94. As a result of evaluating the activation by the thickness of the shielding wall it was found that 89.1% (SAE-AN) and 91.9% (KAERI) of the total radioactivity were exist at a depth of 5 cm. And it was found that 97.7% and 99.05% of the total radioactivity exists at a depth of 10 cm. The relative error between SAE-AN and KAERI is 1.35%, indicating that the analysis results of the two institutions are highly consistent. A core drill was performed on the concrete shielding wall in the cyclotron facility for the technical verification of the quantitative analysis method. A core sample (6 cm in diameter, 10 cm in depth) was cut to a depth of 2 cm and analyzed in the laboratory. The activation distribution(β) was calculated based on the radioactivity level of each depth sample, and it was found to be 16.99. The relative error between the quantitative analysis and the on-site measurement results was 14.95% confirming that the accuracy is relatively high.

The purpose of full system decontamination before decommissioning a nuclear power plant is to reduce radiation exposure of decommissioning workers and to reduce decommissioning waste. In general, full system decontamination removes the CRUD nuclides deposited on the inner surface of the reactor coolant system, chemical and volume control system, residual heat removal system, pressurizer, steam generator tube, etc. by chemical decontamination method. The full system decontamination process applied to Maine Yankee and Connecticut Yankee in the USA, Stade, Obrigheim, Unterweser, Nekawestheim Unit 1 in Germany, Mihama Unit 1 and 2 in Japan, Jose Cabrera Unit 1 in Spain, and Barseback Unit 1 and 2 in Sweden are HP/CORD UV, NP/CORD UV, and DfD. In this study, the quantity of 60Co radioactivity removal, metal removal, ion exchange resin and filter generation according to reactor power, surface area and volume of the full system decontamination flow path, and the decontamination process were compared and analyzed. In addition, the quantity of 60Co radioactivity removal by each nuclear power plant was compared and analyzed with the evaluation results of the 60CO radioactivity inventory of the Kori Unit 1 full system decontamination loops conducted by SAE-AN Enertech Corporation.