[3C09-13] Analysis, Evaluation, System Development

[3C10] Radioactivity calculation of JPDR biological shielding concrete and examination of radioactivity evaluation technique for trench-type disposal

*Mami Kochiyama¹, Akihiro Sakai¹, Chikara Konno¹ (1. JAEA)

Keywords:JPDR biologically shielded concrete, trench-type disposal, radioactive waste, nuclides composition ratio, DORT, ORIGEN-S

We performed activation calculations using DORT and ORIGEN-S for biologically shielded concrete in the power test reactor JPDR. By comparing the calculated values with the measured values of concrete samples,We evaluated the appropriate radioactivity concentration and evaluated the possibility of trench-type disposal and the target nuclides.