Development of ultramicro analysis technology for fuel debris analysis, 21; Actinide separation from irradiated fuels by extraction chromatography

Kazama, Hiroyuki ; Onishi, Takashi ; Ikhwan, F. H.*; Suzuki, Tatsuya*; Sekio, Yoshihiro ; Maeda, Koji ; Koyama, Shinichi ; Konashi, Kenji*; Idemitsu, Kazuya*; Nagai, Yasuyoshi*

Understanding the properties of fuel debris is necessary for decommissioning the Fukushima Daiichi Nuclear Power Station (1F). An essential technique is the chemical analysis of actinide nuclides. In this study, actinide separation from FUGEN irradiated fuel solution was performed by extraction chromatography with tri-n-butyl phosphate impregnated resin (TBP resin). The irradiated fuel was used for a simulant of fuel debris in 1F. The chromatograph behavior revealed that uranium was separated from other actinides selectively.

Language	:	Japanese
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Meeting title	:	日本原子力学会2023年秋の大会
Held date	:	2023/09
Location (city)	:	名古屋
Location (country)	:	日本
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Keywords	:	福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
Research Facility	:	AGF(照射燃料試験施設) ;FMF(照射燃料集合体試験施設)
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Registration No. : BB20230721
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