The objective of this study was to derive derived concentration guideline levels (DCGLs) reflecting the site-specific characteristics of KRR-1&2. A total of 7 nuclides (H-3, C-14, Co-60, Sr-90, Cs-137, Eu-152, and Eu-154) were selected for DCGLs derivation. Radiation dose at the sites was evaluated with RESRAD-ONSITE program. The dose contribution due to direct external exposure was the highest during the entire evaluation period. Ingestion had the second effect. The DCGLs of Co-60 was derived to be 0.051 Bq/g, and DCGLs of Cs-137 was 0.193 Bq/g. The DCGLs of H-3 showed the highest value of 129 Bq/g. The ratio of DCGLs derived by applying site-specific values and default values ranged from 0.27 to 19.6. For six nuclides excluding H-3, KRR-1&2 sites and the overseas NPP sites showed similar DCGLs. H-3 showed large differences in DCGLs from this study and overseas NPPs. The large difference resulted from input parameter values applied to the sites. In conclusion, it is critical to apply site-specific parameter values reflecting the site characteristics to derive DCGLs for decommissioned site clearance. The result of this study can be used as a reference for nuclide selection and DCGLs derivation reflecting the site characteristics when decommissioning nuclear facilities, including nuclear power plants in Korea.

本研究的目的是推导出反映 KRR-1 和 2 特定地点特征的衍生浓度指导水平 (DCGL)。共选择了 7 种核素（H-3、C-14、Co-60、Sr-90、Cs-137、Eu-152 和 Eu-154）用于 DCGL 的推导。使用 RESRAD-ONSITE 程序评估这些部位的辐射剂量。在整个评估期间，直接外照射造成的剂量贡献最高。摄入有第二个影响。Co-60 的 DCGL 为 0.051 Bq/g，Cs-137 的 DCGL 为 0.193 Bq/g。H-3 的 DCGL 值最高，为 129 Bq/g。通过应用站点特定值和默认值得出的 DCGL 的比率范围为 0.27 到 19.6。对于除 H-3、KRR-1 和 2 场址和海外 NPP 场址之外的 6 种核素，DCGLs 相似。H-3 显示本研究的 DCGL 与海外 NPP 存在较大差异。巨大的差异是由于应用于站点的输入参数值造成的。总之，应用反映场地特征的场地特定参数值来推导退役场地清理的 DCGL 至关重要。本研究结果可作为核素选择和 DCGLs 推导的参考，以反映核设施（包括韩国核电厂）退役时的场址特征。