Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Vol. 25 No. 2 (2019): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir

OPTIMASI PARAMETER PEMISAHAN Zr DALAM PEB U3Si2/Al PRA IRADIASI MENGGUNAKAN METODE KROMATOGRAFI PENUKAR ANION

Yanlinastuti Yanlinastuti (Unknown)
Noviarty Noviarty (Unknown)
Iis Haryati (Unknown)
Syamsul Fatimah (Unknown)
Boybul Boybul (Unknown)
Aslina Br. Ginting (Unknown)



Article Info

Publish Date
23 Dec 2024

Abstract

Determination of optimum parameters in the process of zirconium separation from U3Si2/Al fresh fuel solution by anion exchanger chromatography and analysis with UV-Vis spectrophotometer has been carried out. Zirconium is one of isotopes that can be used in the determination of fuel burn-up. The purpose of this study is to obtain optimal parameters of zirconium separation in standard materials as well as U3Si2/Al fresh fuel solution by anion exchanger chromatography. Optimization of Zr separation parameters was carried out using Dowex 1x-8 resin with a variation in weight of 0.5; 1.0; 1.5; 2.0 and 2.5 g, acidity of H2SO4 at 1; 2; 3; 4; 5 and 6 M, standard feed concentrations of Zr at 50; 100; 150 and 200 ppm and flow rate of 3M H2SO4 elution at 0.1; 0.3; 0.5; 0.7 and 0.9 mL/minute. To the Zr effluent as the result of separation was added Arsenazo III 0.1% as complexing agent, and subsequent analysis with UV-Vis spectrophotometry was done at a wavelength of 665.3 nm. The measurement results show that the optimal parameters of Zr separation are the use of 1.5 g resin with resulting recovery of 70.79%, acidity of 3M H2SO4 with recovery of 83.94%, feed concentration of 150 ppm with recovery of 87.64% at a flow rate of 0.5 mL/minute. When those optimal parameters were used in Zr separation from U3Si2/Al fresh fuel solution, the recovery obtained was 96.23%. These optimized parameters can also be used to separate Zr from U3Si2/Al irradiated fuel solution.

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Journal Info

Abbrev

urania

Publisher

Subject

Description

Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir is a scientific publication platform that presents experimental research and development studies on the nuclear fuel cycle, covering radiation physics and chemistry, reactor engineering, nuclear safety and security, nuclear forensics, and radioactive ...