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All Journal Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Ghoib Widodo
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EFFECT OF CURRENT, TIME, TYPE OF FEED AND CATHODE ON ELECTROPLATING PROCESS OF URANIUM SOLUTION Sigit; Ghoib Widodo; Bangun Wasito; Kris Tri Basuki; Fahrunissa
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 1 (2017): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2017.23.1.3155

Abstract

Electroplating of uranyl nitrate and process effluent has been carried out in order to collect uranium contained therein using Pt/Pt and Pt/SS electrodes at various current and time values. The materials used as electrode were Pt (platinum) and SS (Stainless Steel). Feed solution of 250 mL was entered into a beaker glass equipped with Pt anode - Pt cathode or Pt anode - SS cathode and connected to direct current source from DC power supply at various current values and for various time periods so that uranium precipitated and deposited onto the cathode. Upon deposition completion, the cathode was removed and weighed to determine weight of precipitates, while the solution was analyzed to determine uranium concentration decrease after electroplating process. The experiment shows that a relatively good time to acquire uranium deposit at the cathode was 1 hour at 7 amperes, with uranyl nitrate as feed and Pt (platinum) as cathode. In these conditions, uranium deposit attached to the cathode amounted to 74.96% of the original weight of uranium oxide in the feed or 206.5 mg by weight. The use of Pt cathode for uranyl nitrate feed, and SS and Pt cathodes for effluent feed resulted in uranium specific weight at the cathode of 12.99 mg/cm2, 2.4 mg/cm2 and 5.37 mg/cm2 respectively for 7 Ampere current for 1 hour electroplating time.
PROSES EKSTRAKSI-STRIPPING UO2(NO3)2 BERIMPURITAS HASIL PELARUTAN DARI YELLOW CAKE Anwar Muchsin; Ghoib Widodo
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 1 (2017): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2017.23.1.3172

Abstract

Uranyl nitrate/UO2(NO3)2 is a basic material/bait that is used as fuel both a research reactor fuel and power reactors. The process of extraction-stripping necessary to UO2 (NO3)2, because in the UO2(NO3)2 is still contained impurities are entrained during the dissolution process yellow cake. To obtain a solution of UO2 (NO3)2 which meets the requirements of pure nuclear (nuclear grade), it should be a process of purification by extraction-stripping using three (3) parameters of the feed flow rate, the acidity of the feed to the extraction process, and acidity in the stripping process. The mechanism of the extraction process takes UO2 (NO3)2 will go into the organic phase TBP, whereas impurity are in the water phase (refined). Uranium in the organic phase stripping process is carried out by determining the acidity (as a parameter), in order to obtain a mixed solution UO2 (NO3)2 pure nuclear (nuclear grade). As a bait used uranyl nitrate solution with levels of uranium amounted to 225.6282 gU/L. The results extraction process obtained the rate of feed water 15 L/h, the acidity of the feed to the extraction process by 3 M and obtained levels of uranium amounted to 48.5365 gU/L, while the stripping process is obtained UO2 (NO3)2 amounted to 64.7860 gU/L the acidity of 0.04 M.
Co-Authors Anwar Muchsin Bangun Wasito Fahrunissa Kris Tri Basuki Sigit