Stabilization treatment of nuclear fuel material contained with organic matter

Senzaki, Tatsuya; Arai, Yoichi; Yano, Kimihiko; Sato, Daisuke; Tada, Kohei; Ogi, Hiromichi*; Kawanobe, Takayuki*; Ono, Shimpei; Nakamura, Masahiro; Kitawaki, Shinichi; et al.

JAEA-Testing 2022-001, 28 Pages, 2022/05

JAEA-Testing-2022-001.pdf:2.33MB

In preparation for the decommissioning of Laboratory B of the Nuclear Fuel Cycle Engineering Laboratory, the nuclear fuel material that had been stored in the glove box for a long time was moved to the Chemical Processing Facility (CPF). This nuclear fuel material was stored with sealed by a polyvinyl chloride (PVC) bag in the storage. Since it was confirmed that the PVC bag swelled during storage, it seems that any gas was generated by radiolysis of the some components contained in the nuclear fuel material. In order to avoid breakage of the PVC bag and keep it safety for long time, we began the study on the stabilization treatment of the nuclear fuel material. First, in order to clarify the properties of nuclear fuel material, radioactivity analysis, component analysis, and thermal analysis were carried out. From the results of thermal analysis, the existence of organic matter was clarified. Then, ion exchange resin with similar thermal characteristics was selected and the thermal decomposition conditions were investigated. From the results of these analyzes and examinations, the conditions for thermal decomposition of the nuclear fuel material contained with organic matter was established. Performing a heat treatment of a small amount of nuclear fuel material in order to confirm the safety, after which the treatment amount was scaled up. It was confirmed by the weight change after the heat treatment that the nuclear fuel material contained with organic matter was completely decomposed.

MA recovery experiments from genuine HLLW by extraction chromatography

Watanabe, So; Senzaki, Tatsuya; Shibata, Atsuhiro; Nomura, Kazunori; Koma, Yoshikazu; Nakajima, Yasuo

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 6 Pages, 2011/12

Extraction chromatography experiments with two promising flow-sheets on genuine high level liquid wastes were carried out for demonstrating the feasibility of the method. One flow-sheet consists of CMPO/SiO-P and HDEHP/SiO-P adsorbent columns, and the other consists of TODGA/ SiO-P and isoHex-BTP/SiO-P adsorbent columns. Although recovery yields of MA and decontamination factors of FPs obtained by those experiments were lower than the required values, the second flow-sheet is expected to achieve the required performance providing that some minor improvements on the flow-sheet or the adsorbents are applied.

Optimization in flow-sheet of extraction chromatography with CMPO and HDEHP impregnated adsorbents

Watanabe, So; Senzaki, Tatsuya; Shibata, Atsuhiro; Nomura, Kazunori; Nakatani, Kiyoharu*; Horiuchi, Yusuke*; Arai, Tsuyoshi*; Matsuura, Haruaki*

no journal, , 

no abstracts in English