Abstract
In uranium enrichment plant decommissioning, it is important to treat and dispose the gas centrifuge reasonably. At the Ningyo-Toge Environmental Engineering Center of JAEA, it has been planned to carry out IF7 treatment for the gas centrifuge in the uranium enrichment plant for decontamination before dismantling. In order to carry out this IF7 treatment, a nondestructive measurement technology to estimate the uranium weight in the interior of the gas centrifuge was needed. However, it was difficult to estimate exactly uranium weight using former methods. Therefore, in this study, we investigated a new nondestructive measurement. As a result, we succeeded in constructing theoretically the methodology using γ-ray intensity measured outside the gas centrifuge and MCNP code. Furthermore, the UF6 and IF5 mixture was recovered by IF7 treatment. A technology to separate and refine IF5 from this mixture was needed in order to use as a material of IF7 gas. Therefore, in this study, we carried out IF5 separation and refinement examination. This paper shows the investigation result of reasonable separation condition and the full-scale examination result. As a result, it could be proved that 86% of IF5 was separated and refined from UF6 and IF5 mixture.
