[3H05-10] Technologies for Dismantling, Decontamination and Evaluation

[3H10] Development of general-purpose clearance radioactivity concentration measurement

(1)Investigation of issue in nuclide selection from Rule 274 nuclides

*Masato Watanabe¹, Kouji Hayashi², Ryouji Mizuno², Tomoo Horie³ (1. Chubu Electric Power, 2. Chuden CTI, 3. Techno Chubu)

Keywords:clearance, BWR, Radiation contamination, Secondary contamination, Activation calculation

For the purpose of developing a clearance measurement evaluation method for the removed objects generated during plant operation and decommissioning, it was investigated whether the radioactivity concentration of the nuclide to be evaluated can be output by activation calculation. The nuclides to be evaluated were Rule 274 nuclides for power reactor facilities. In the activation calculation, ORIGEN2.2UPJ (JENDL 4.0) and ORIGEN-S (Scale 6.1: ENDF / B-VII) were used.