Analysis of Cm contained in irradiated fuel of experimental fast reactor "JOYO"; Development of the analytical technique and measurement of Cm

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 4.0lO atom%, small amount of Cm was generated and Cm isotopic ratio was constant above burn-up 60GWd/t.

Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels, 6; ARES-MOX transient program for irradiated MOX fuels in TREAT

Ozawa, Takayuki; Hirooka, Shun; Kato, Masato; Smuin, T. J.*; Jensen, C. B.*; Woolstenhulme, N. E.*; Wachs, D. M.*

no journal, , 

The ARES-MOX transient program is planned in TREAT by using MOX fuels irradiated in SPA-2 irradiation tests in EBR-II, which was conducted in 1984-1994 under the international collaboration between US and Japan, and have been stored in the current INL. The MOX fuels irradiated up to the maximum burnup of about 130 GWd/t in EBR-II includes the solid FP content of about 10 wt.%. In this program, the objectives are to acquire not only valuable data to develop the FCMI threshold for high-burnup annular MOX fuels but also knowledge about irradiation behavior of FP at transient. The overview of ARES-MOX program, schedule and outcomes expected from fuel performance calculation for annular MOX fuels irradiated in EBR-II will be introduced here.