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JNC TN8400 2001-022, 60 Pages, 2001/03
JNC-TN8400-2001-022.pdf:1.31MB
A numerical simulation code for the TRUEX (Transuranium Extraction) process was developed. Concentration profiles of americium and europium were calculated for some experiments of the counter current extraction system those were carried out in CPF (Chemical Processing Facility) by using the code. Calculation profiles were in agreement with the experimental results. Operational conditions were also examinted for the americium recovery experiment by the TRUEX process carried out in the Plutonium Fuel Center. It was shown that lowering the concentration of nitric acid in the scrub solution and decreasing the flow rate of solvent and strip solution was effective for improving the performance of the stripping step and reducing the volume of the waste solution. In order to find the optimum conditions for various experiments, this simulation code was modified to calculate the concentration profiles of other metal elements such as zirconium and iron and the effect of oxalic acid on the extraction behavior of the metal elements. The calculated concentration profiles of americium and europium were varied by this modification. In the experiment at CPF, the calculations were carried out to obtain recovery ratio of americium in the product stream with the amount of oxalic acid added to the process. This calculation result showed that it was possible to improve the performance of decontamination of fission products by increasing oxalic acid concentration added to the process. The calculation was also carried out for finding the optimum conditions of oxalic acid concentration added to the europium recovery process.
Fujiwara, Kenso; Iijima, Kazuki
no journal, ,
Regarding the waste generated by the decommissioning process of the 1F, it is necessary to grasp the properties such as inventory. In order to contribute to understanding the properties of radionuclides, the concentrations of transuranium elements and fission products in the soil will be measured. By considering the diffusion effect from the concentration distribution of nuclides in the depth direction, the ground surface inventory evaluation can be expected. In this study, the soil outside the specified nuclear facility located on the south side of the 1F was sampled with a scraper plate to a depth of about 15 cm every 1 cm, and Cs-134 and 137 were measured by gamma-ray measurement, and Sr-90 and were measured by beta-ray measurement. The concentrations of Pu, Am, and Cm were determined by alpha-ray. The nuclide profile obtained was converted into the nuclide concentration deposited on the surface at the time of the accident, and inventory evaluation was performed.