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Osaka, Masahiko; Koyama, Shinichi; Mitsugashira, Toshiaki; Morozumi, Katsufumi; Namekawa, Takashi
JNC TN9400 2000-058, 49 Pages, 2000/04
JNC-TN9400-2000-058.pdf:1.22MB
The analytical technique for Cm contained in a MOX FUEL was developed and analysis of Cm contained in irradiated fuel of experimental fast reactor "JOYO" was carried out, to contribute to evaluation of transmutation characteristics of MA nuclide in the fast reactor. The procedure of ion-exchange separation of Cm with nitric acid-methanol mixed media essential for the isotopic analysis in irradiated MOX fuel was adopted considering for being rapid and easy. The fundamental test to grasp separation characteristics of this procedure, such as Cm elution position and separation capacity between Cm and Am or Eu, was carried out. ln applying this procedure to the analysis of Cm contained in actual specimen, separation condition was evaluated and optimized, and the procedure consist of impurity removal and Am removal process was devised. This procedure resulted in high recovery rate of Cm and high removal rate of Am and impurity which becomes a problem in sample handling and mass-spectrometry such as Eu and Cs. The Cm separation test from irradiated MOX fuel was carried out using this technique, and Cm isotopic ratio analysis was enabled. The analytical technique for Cm contained in irradiated MOX fuel was established using the procedure of ion-exchange separation with nitric acid-methanol mixed media. The analysis of Cm contained in irradiated MOX fuel of experimental fast reactor "Joyo" was carried out. As a result, it was revealed from measured data that Cm content rate was 1.4
4.0
lO
atom%, small amount of 
Cm was generated and Cm isotopic ratio was constant above burn-up 60GWd/t.
Miyamoto, Yutaka; Yasuda, Kenichiro; Magara, Masaaki
no journal, ,
In order to analyse the environmental records of key elements including radioactive isotopes which originates from nuclear bomb tests and accidental releases from nuclear power plants, the authors accomplished the development of technique for automatic and sequential separation of less than nano grams of ultra-trace U, Th, Pb, the lanthanides, and Pu using a single anion-exchange column and mixed media consisting of highly pure acids. The separation performance of ion-exchange column was evaluated using the spikes and a reference solution, and the automatic separation system was served for the elemental and isotopic analyses of ultra-trace elements in the tree ring samples.
Komada, Ryo*; Yabe, Yuki*; Arai, Tsuyoshi*; Sato, Fuminori
no journal, ,
no abstracts in English