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SEPARATION OF ZIRCONIUM AND HAFNIUM WITH SIR METHOD’S (ADSORPTION AND DESORPTION ION EXCHANGE) Dwi Biyantoro; Noor Anis Kundari; Nofriady Aziz
Jurnal Forum Nuklir JFN VOL 11 NO 1 MEI 2017
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (450.514 KB) | DOI: 10.17146/jfn.2017.11.1.4008

Abstract

Precence of hafnium is  more  than 100 mg/kg making it impossible to use as cladding material in nuclear reactor, because of its high adsorption cross section thus inhibite the nuclear fission. The objective of this research is to separate Zr – Hf using SIR method that is by impregrnating extracts to  resin. Extractants used are TBP and D2EHPA, resin used is XAD – 7, and feed used is Zirconium Basic Sulphate (ZBS). In this research is done variation compotition SIR, optimation process adsorption and desoprtion SIR and determintionof equation model in adsorption SIR. The result of this research is composition SIR the most effective for separation Zr – Hf is 5 : 5 for dry method’s and 7 : 3 for wet metode’s, model of equation for Zr nearly Langmuir model, model of equation for Hf nearly Freundlich model and adsorption result effenctively is comparation feed : SIR yaitu 10 mL : 1,5 g (1 : 1,5) with separation factor 30.12 ; separation efficiency Zr 31.47 % and separation efficiency Hf  42.06%.
PEMISAHAN Ce DAN Nd MENGGUNAKAN RESIN DOWEX 50W-X8 MELALUI PROSES PERTUKARAN ION Dwi Biyantoro; Kris Tri Basuki; Muhadi Ayub Washito
GANENDRA Majalah IPTEK Nuklir Volume 9 Nomor 1 Januari 2006
Publisher : Website

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (170.985 KB) | DOI: 10.17146/gnd.2006.9.1.170

Abstract

PEMISAHAN Ce DAN Nd MENGGUNAKAN RESIN DOWEX 50W-X8 MELALUI PROSES PERTUKARAN ION.Telah dilakukan penelitian pemisahan Ce dan Nd menggunakan kolom penukar ion yang berisi resin Dowex 50W-X8ukuran 100 – 200 mesh dan eluen EDTA. Penelitian ini bertujuan untuk mengetahui keberhasilan proses pemisahanCe dan Nd menggunakan kolom penukar ion. Pemisahan ini dilakukan dengan menggunakan kolom gelasberdiameter 0,4 cm, panjang 95 cm, umpan campuran Ce dan Nd pada pada kecepatan alir EDTA 0,05 ml/menit. Eluatditampung secara fraksional setiap 5 ml kemudian dianalisis menggunakan spektrometer pendar sinar-X. Dari hasilpenelitian diperoleh nilai kapasitas resin Dowex 50W-X8 = 5,28 mgrek/g, resolusi Ce-Nd = 1,47, dan faktor pemisahanCe-Nd = 5,16 pada perbandingan umpan Ce dan Nd = 20 : 1.
STUDI OPERASI RESIN PENUKAR ION DALAM SISTEM PURIFIKASI AIR PRIMER PWR Dwi Biyantoro; Kris Tri Basuki; Subagiono Subagiono
GANENDRA Majalah IPTEK Nuklir Volume 9 Nomor 1 Januari 2006
Publisher : Website

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (161.622 KB) | DOI: 10.17146/gnd.2006.9.1.166

Abstract

STUDI OPERASI RESIN PENUKAR ION DALAM SISTEM PURIFIKASI AIR PRIMER PWR. Telah dilakukan studioperasi resin penukar ion dalam sistem purifikasi air primer PWR. Air pendingin reaktor yang pada awalnya sesuaidengan persyaratan setelah pengoperasian reaktor sering kualitasnya berubah, sehingga harus dimurnikan. Unsurunsurpengotor dalam air primer PWR diidentifikasi sebagai penyebab pengotor seperti korosi, pelepasan produk fisi(Cs137, Sr90, Co60,C14, Tc99), dan pelepasan kembali unsur oleh resin penukar ion. Air yang sudah tidak sesuai denganpersyaratan reaktor kemudian dilakukan pemurnian mengunakan resin penukar ion. Resin-resin ini digunakan untukmenghilangkan kotoran yang tidak diinginkan, seperti material-material radioaktif atau pencemaran yang lain yangdapat secara potensial merugikan peralatan atau merusak bahan bakar reaktor. Resin-resin penukar ion yangdirekomendasikan digunakan dalam reaktor PWR (komersial) untuk purifikasi adalah sebagai berikut: penukarpenukarkation : Resin IRC-50, Resin 200-H, dan Resin 650-C, penukar-penukar anion : Resin A-550 dan Resin 900-OH, dan penukar campuran : Resin 21H (ECODEX P-202-H). Resin penukar ion tersebut adalah termasuk polimerorganik sintetis yang mempunyai matriks/network yang berupa polistiren (PS) dan pengikat silangnya divinil benzen(DVB). Resin polistiren – divinilbenzen (PSDVB) mempunyai sifat-sifat yang menguntungkan sebagai penukar ionseperti kapasitas penukaran yang baik, selektif, ukuran partikel dengan ukuran tertentu, kestabilan resin tinggi padaberbagai pH, laju pertukaran ion yang cepat, dan limbah yang dihasilkan relatif kecil.
IDENTIFIKASI FASA PADA PELET BAHAN BAKAR U-ZrHx HASIL PROSES SINTER DENGAN ATMOSFER NITROGEN Masrukan; Jan Setiawan; Dwi Biyantoro
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 3 (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.2017.23.3.3641

Abstract

Phases identification of U-ZrHX fuel pellets sintered under nitrogen atmosphere has been carried out. This sintering process is intended to obtain higher density pellets that meet the requirements for use as a fuel in pressurized water reactor (PWR). The results of this study are expected to be used for the determination of phase and density changes occurred in U-ZrHx pellets at various Zr concentrations after sintering at various temperatures. PWR fuel from U-ZrHx pellet needs to be sintered to increase its density. At first, pellets made from U-ZrHx powder with Zr composition of 35, 45 and 55 wt.% through a pressing process at a pressure of 509-637 MPa. The resulted U-ZrHx green pellets were subsequently sintered under nitrogen gas atmosphere at 1200 °C and 1300 °C for a fixed sintering time of one hour. Phase analysis of the sintered U-ZrHx pellets was done by X-ray diffraction (XRD) technique and the data obtained were processed by using HighScore Plus software. The test results with XRD indicate the formation of phases such as U(ZrHr2), UO3, UO2, and Zr. The UO2 and Zr phases were characterized for their density, lattice parameter and percentage of weight. In this experiment it is desired to obtain U-ZrHx with high density without the formation of many phases. Density measurement shows that the density of zirconium metal and UO2 decreases with increasing sintering temperature (from 1200 °C to 1300 °C), while the lattice parameter increases with increasing sintering temperature. Data calculation of weight percentage for sintering at 1300 °C shows that the percentage values of the resulted zirconium metal and uranium dioxide are the closest to their theoretical calculation results.
PEMISAHAN Zr – Hf SECARA SINAMBUNG MENGGUNAKAN MIXER SETTLER Dwi Biyantoro; Isyuniarto; Masrukan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 3 (2016): 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.2016.22.3.3184

Abstract

Separation of Zr - Hf continuously using mixer settler 16 stage has been done. The feed solution is zircon nitrate concentration of Zr = 30786 ppm and Hf = 499 ppm. As the solvent used extractant 60 % TBP in 40 % kerosene. Nitric acid solution used srubbing 1 M. The feed entered into stage to 5 is contacted with solvents direction on the stage to 16 and the scrubbing solution enter the stage to 1. The purpose of this study is to separate Zr and Hf of the results from the process of zircon sand using solvent TBP using 16 stage mixer settlers. Analysis of the feed and the results of the separation process for zirconium (Zr) using X-ray fluorescence instrument which hafnium (Hf) using Neutron Activation Analysis (AAN). Parameter study done of acidity variation of nitric acid in the feed and time variation in various stirring speed. From the research the separation of Zr-Hf, the optimum conditions in acidity feed 4 N HNO3, equilibrium was received after 3 hours, and stirring speed of 3300 rpm obtained extract of zircon (Zr) concentration = 28577 ppm (efficiency of Zr = 92,76 %) with impurities of hafnium (Hf) = 95 ppm.