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PENENTUAN BERAT ISOTOP CESIUM DAN URANIUM DALAM PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 Yanlinastuti Yanlinastuti; Sutri Indaryati; Boybul Boybul; Supardjo Supardjo; Aslina Br. Ginting
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 26, No 2 (2020): Juni 2020
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Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2020.26.2.5874

PENENTUAN BERAT ISOTOP CESIUM DAN URANIUM DALAM PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 BURN UP 40%. Pelat elemen bakar (PEB) U3Si2/Al densitas 4,8 gU/cm3 telah diiradisi di Reaktor Serba Guna (RSG-GAS) dengan burn up 40%. Selama bahan bakar tersebut diradiasi di reaktor menghasilkan beberapa isotop hasil fisi seperti cesium, uranium dan isotop lainnya. Besarya isotop hasil fisi tersebut digunakan dalam perhitungan burn up untuk mengetahui unjuk kerja bahan bakar selama diradiasi di reaktor. Oleh karena itu, berat cesium dan uranium harus diketahui secara kuantitatif melalui proses pemisahan analisis fisikokimia. Pelat elemen bakar U3Si2/Al densitas 4,8 gU/cm3 bagian Middle dipotong secara duplo dengan berat M-1=0,056 g dan M-2=0,075 g, kemudian dilarutkan menggunakan HCl 6N dan HNO3 6N. Larutan PEB pasca iradiasi dipipet sebanyak 100 µL dimasukkan masing-masing kedalam 2 mL larutan HNO3, H2SO4 dan HCl 0,1N, selanjutnya dilakukan pemisahan cesium menggunakan metode penukar kation dengan penambahan 1000 mg zeolit Lampung. Hasil pemisahan diperoleh isotop cesium terikat dengan zeolit dalam fasa padat sedangkan uranium berada dalam fasa cair. Isotop cesium dalam fasa padat maupun dalam fasa cair diukur dengan spektrometer-g selama 10000 detik. Hasil pengukuran diperoleh spektrum 134Cs pada energi 604,7 dan 795,8 keV serta isotop 137Cs pada 661,7 keV. Sementara itu, pemisahan uranium dalam fasa cair dilakukan menggunakan metode kolom penukar anion dengan penambahan 1200 mg resin Dowex. Hasil pemisahan diperoleh spektrum isotop 238U pada energi 4,1943 MeV, 235U pada 4,397 MeV, 236U pada energi 4,494 MeV dan isotop 234U pada 4,777 MeV. Hasil evaluasi dari luas spektrum tersebut diperoleh berat isotop 137Cs dalam 0,056 g potongan PEB U3Si2/Al sebesar 4,08E-05 g; 4,53E-05 g dan 4,53E-05 g, sedangkan isotop 134Cs sebesar 4,84E-08 g; 5,30E-08 g dan 5,20E-08 masing-masing dalam pelarut HNO3; H2SO4dan HCl. Sementara itu, berat isotop 137Cs dalam 0,075 g potongan PEB U3Si2/Al diperoleh sebesar 5,93E-05 g; 5,90E-05 g dan 5,88E-05 g, sedangkan berat isotop 134Cs sebesar 5,23E-07 g; 5,29E-07g dan 5,08E-07g untuk masing-masing pelarut HNO3; H2SO4dan HCl. Berat isotop 238U,235U, 236U dan 234U dalam 0,056 g potongan PEB U3Si2/Al diperoleh sebesar 6,45E-03 g; 2,57E-03 g; 2,42E-06 g; dan 1,90E-05 g, sedangkan dalam 0,075 g PEB diperoleh sebesar 7,41E-03 g; 2,40E-03 g; 2,91E-06 g; dan 2,17E-05 g. Berat isotop 134Cs, 137Cs, 238U,235U, 236U dan 234U dalam 0,056 g PEB dan 0,075 g potongan PEB U3Si2/Al relatif sama dan selanjutnya digunakan sebagai data masukan untuk perhitungan burn up.Kata kunci: PEB U3Si2/Al pasca iradiasi, pemisahan, kation-anion, cesium, uranium.

PEMISAHAN CESIUM DALAM BAHAN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 BURN UP 60% POTONGAN BOTTOM Ariyanti Saputri; Sutri Indaryati; Iis Haryati; Yanlinastuti Yanlinastuti; Hanifah Rifaatul Mahmudah; Aslina Br. Ginting
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 27, No 3 (2021): Oktober, 2021
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2021.27.3.6571

PEMISAHAN CESIUM DALAM BAHAN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 BURN UP 60% POTONGAN BOTTOM. Telah dilakukan pemisahan cesium dalam bahan bakar U3Si2/Al densitas 4,8 gU/cm3 burn up 60% menggunakan bahan zeolit Lampung pada metode penukar kation. Burn up bahan bakar pasca iradiasi dapat ditentukan dengan indikator burn up menggunakan isotop cesium. Pemisahan bertujuan untuk mendapatkan berat cesium yang akurat sehingga perhitungan nilai burn up secara merusak juga dapat dilakukan secara tepat. PEB U3Si2/Al dipotong pada bagian Bottom secara duplo lalu ditambahkan pelarut HCl 6 N dan HNO3 6N. Satu mL larutan bahan bakar U3Si2/Al dimasukkan ke dalam botol vial dan ditransfer dari hotcell 109 ke laboratorium radiasi aktivitas sedang (R.135). Larutan bahan bakar U3Si2/Al diencerkan menjadi 25 mL dan dipipet 50 µL ke dalam vial secara duplo dan ditambahkan 1000 mg zeolit Lampung, kemudian dilakukan pemisahan 134Cs dan137Cs dari 235U dengan metode penukar kation secara batch selama 60 menit. Hasil pemisahan diperoleh isotop 134Cs dan 137Cs dalam fasa padat, sedangkan uranium (238U, 235U, 234U) dan isotop lainnya dalam fasa cair. Besarnya berat isotop 134Cs dan137Cs selanjutnya diukur menggunakan spektrometer-γ. Hasil pemisahan diperoleh berat isotop 137Cs dan 134Cs dalam larutan PEB U3Si2/Al densitas 4,8 gU/cm3 burn up 60% potongan Bottom masing-masing B-1=0,00003283 g/0,036gPEB dan B-1= 0,000000147 g/0,036gPEB, sedangkan untuk potongan B-2=0,00003290 g/0,037gPEB untuk 137Cs dan B-2= 0,000000222 g/0,037gPEB untuk 134Cs. Pemisahan cesium dalam 50 µL larutan PEB U3Si2/Al burn up 60% potongan Bottom dengan metode penukar kation menggunakan zeolit Lampung seberat 1000 mg diperoleh hasil yang baik.Kata kunci: U3Si2/Al densitas 4,8 gU/cm3, burn up 60%, cesium, pemisahan.

OPTIMASI PARAMETER PEMISAHAN Zr DALAM PEB U3Si2/Al PRA IRADIASI MENGGUNAKAN METODE KROMATOGRAFI PENUKAR ANION Yanlinastuti Yanlinastuti; Noviarty Noviarty; Iis Haryati; Syamsul Fatimah; Boybul Boybul; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 2 (2019): 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.2019.25.2.5508

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.

PEMISAHAN DAN ANALISIS CESIUM DALAM PEB U3Si2/Al TMU 2,96 gU/cm3 PASCA IRADIASI DENGAN METODE PENGENDAPAN CHLOROPLATINATE Arif Nugroho; Boybul Boybul; Sutri Indaryati; Iis Haryati; Rosika Kriswarini; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 2 (2019): 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.2019.25.2.5466

Fuel burnup is an important parameter for determining the quality and integrity of irradiated nuclear fuel. The most important parameters in the calculation of burnup is the separation process and 137Cs content analysis sampled from the irradiated plate fuel. This research has conducted separation and analysis of the 137Cs contained in irradiated U3Si2/Al plate by chloroplatinate precipitation method. This method requires that the sample has to be made free from elements that may interfere with the precipitation process. The separation is done by precipitation of 137Cs isotope in the form of Cs2PtCl6. The precipitation process uses CsNO3 as non-active carrier with varied weight of 0.0263; 0.0501; 0.0754; 0.1036 ; 0.2064; 0.3020, and 0.4017 g. The CsNO3 carrier is added in order to obtain more ammount of precipitate of Cs in the form of Cs2PtCl6 because CsNO3 has similar chemical properties with 137Cs in uranyl nitrate solution. The 137Cs isotope is coprecipitated in Cs2PtCl6, and γ-spectrometry is used in the determination of the content of 137Cs in Cs2PtCl6 precipitate. The separation results show that addition of 0,1036 g CsNO3 has recovered 0.000328 g/g-sample of 137Cs from 0.000465 g/g-sample in irradiated U3Si2/Al solution, or a recovery of 70.4753%. Recovery value by this method is still lower when compared to other 137Cs separation methods due to longer steps of separation process, which may cause many errors in the sample preparation process.

PEMBUATAN STANDAR CESIUM DARI LARUTAN PEB U3Si2/Al PASCA IRADIASI DENSITAS 2,96 gU/cm3 DENGAN METODE PENGENDAPAN CsClO4 Aslina Br. Ginting; Boybul Boybul; Arif Nugroho; Yanlinastuti Yanlinastuti; Noviarty Noviarty; Gatot Wurdiyanto; Hermawan Chandra
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 25 No. 2 (2019): 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.2019.25.2.5457

A considerable amount of irradiated nuclear fuel solutions exists in the hot cell area of Radiometallurgy Instalation (IRM). These solutions were generated from sampling activities for burnup test. The solutions cannot be disposed due to the present of 137Cs isotope and other heavy elements that have a long half time, but the solutions can be used as a secondary source of 137Cs standard for analysis purposes. Post-irradiation fuel analysis is always conducted by a valid method and with a calibrated spectrometer-γ. The standard used in the calibration of spectrometer-γ energy or activity is 137Cs isotope. There has been some restriction in the use of spectrometer-γ because spectrometer-γ calibration cannot be performed routinely due to the unavailability of standard sources. The availability of 137Cs isotope for R&D is still dependent on abroad suppliers. Therefore, in this research, PTBBN and PTKMR aim to develop a secondary standard source of 137Cs isotope with 10330 ± 411 Bq activity. The standard source was obtained from a solution of 137Cs separated from U3Si2/Al irradiated fuel. The separation was done by precipitation method with CsNO3 and HClO4 as the carrier. The result of the separation is 137CsClO4 precipitate, dried and weighed for obtaining greater activity and measured with a spectrometer-γ. The dried precipitate 137CsClO4 was subsequently packed as closed standard source (shield source). This standard sourced was certified by PTKMR as secondary standard isotope of 137Cs and is ready to be used for energy calibration of spectrometer-γ.

PEMISAHAN CESIUM DALAM PEB U3Si2/Al PASCA IRADIASI DENGAN METODE KOLOM PENUKAR KATION MENGGUNAKAN RESIN DOWEX Arif Nugroho; Dian Anggraini; Boybul Boybul; Sutri Indaryati; Rosika Kriswarini; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 2 (2018): 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.2018.24.2.4306

The burn up calculations of nuclear fuel by destruction method can be determined from the analysis of 137Cs isotope, as fission product. For this reason, the separation of 137Cs isotopes from uranium in irradiated fuel element plates of U3Si2/Al (PEB) needs to be done. The separation of 137Cs was done by using cation exchange column method with Dowex resin with weight variation of 1; 2; 3; 4; 5 and 6 g. This study aims to determine the content of 137Cs in irradiated fuel element plates of U3Si2/Al (PEB) using the cation exchange column method with Dowex resin to be compared with the result of 137Cs separation by cation exchange column method using Lampung zeolite and CsClO4 precipitation method. The irradiated fuel element plates of U3Si2/Al (PEB) PEB U3Si2/Al with a density of 2.96 gU/cm3 from the middle part of RI-SIE2 code and side plate 20 IDA 0045 was taken with weight 0.1103 g and dissolved with HCl 6N and HNO3 6N to obtain uranil nitrate solution. The U3Si2/Al post irradiated solution was 150 μL was added with 2 mL aquadest and added with Cs carrier 20 μL and 1 mL HCl 12 M. The solution mixture was used as feed into the anion exchange column (first column) containing the R-Cl resin –with the wight variation about 1; 2; 3; 4; 5 and 6 g. The effluent from the anion exchange column was introduced into the cation exchange column (second column) which contained R-NH4+ resin with weight variation of 1; 2; 3; 4; 5 and 6 g. The bounded 137Cs isotope in R-NH4+ resin in the column was being eluted using 1 M HCl of 15 mL and being vaporized until the volume reach ± 2 mL. The quantity of the 137Cs isotope in the effluent was measured by using a gamma spectrometer with a counting time of 500 s. The 137Cs isotope content in irradiated fuel element plates of U3Si2/Al with the density 2.96 gU/cm3is 0.000445 g/gPEB and the parameter of separation 137Cs with cation exchange column method using Dowex resin weighing 2 g with recovery is 98.67%. The result of separation of 137Cs by cation exchange column method is not much different from the result of separation 137Cs by cation exchange method and CsClO4 precipitation method. The 137Cs obtained can then be used for burn up calculations.

KARAKTERISASI PADUAN AlMgSi UNTUK KELONGSONG BAHAN BAKAR U3Si2/Al DENSITAS URANIUM 5,2 gU/cm3 Aslina Br. Ginting; Supardjo; Yanlinastuti Yanlinastuti; Dian Anggraini; Boybul Boybul
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 1 (2018): 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.2018.24.1.4016

Increase in uranium density from 2.96 gU/cm3 to 5.2 gU/cm3 of U3Si2/Al fuel requires a compatible cladding. High density fuel possesses high hardness value, and the use of AlMg2 as cladding material may cause dog bone during rolling process. In addition to dog bone phenomena, swelling can also occur during the use of nuclear fuel in the reactor due to rising in fission products and burn up. For this reason, substitution of cladding material should be determined to suit the high density U3Si2/Al fuel. This research deals with the characterization of AlMgSi as a candidate for AlMg2 substitution. The characterization includes thermal analysis with DTA (Differential Thermal Analysis) dan DSC (Differential Scanning Calorimetry), hardness test with macrohardness tester, microstructure examination with SEM (Scanning Electron Microscope), and corrosion analysis by heating at 150 °C for 77 hours in an autoclave. Analysis results show that both AlMgSi and AlMg2 share stable heat compatibility with U3Si2/Al up to 650 °C. AlMgSi cladding has a hardness value of 115 HVN, higher than that of AlMg2, which is 70.1 HVN. Microstructure examination shows that AlMgSi has better morphology of interface bonding than AlMg2. Corrosion rate analysis also indicates that AlMgSi has lower corrosion rate. The results of thermal, hardness, microstructure and corrosion characterization reveal that the U3Si2/Al fuel of 5.2 gU/cm3 suits better with AlMgSi than AlMg2.

ANALISIS METALOGRAFI PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 2,96 gU/cm3 PASCA IRADIASI Maman Kartaman Ajiriyanto; Aslina Br. Ginting; Junaedi
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 24 No. 1 (2018): 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.2018.24.1.4010

Metallographic analysis of U3Si2/Al fuel element plate has been performed in hot cell. The purpose of metallographic analysis is to study changes in PEB U3Si2/Al microstructure and AlMg2 cladding thickness after irradiation in reactor until burn up of 56%. The fuel element plate of irradiated U3Si2/Al was cut in top, middle and bottom positions with each size around 5x5x1,37mm. Metallographic preparation starts from sample cutting using cutting machine with low speed and sample mounting, grinding and polishing in hot cell 104–105. Sample mounting was done by using resin for more than 10 hours followed by grinding with sandpapers up to grit size of 2400 and polishing with diamond paste of size 3 to 1 micron at a rotational speed of 150 rpm for 5 minutes. Microstructure observation was performed with optical microscope in hot cell 107 at 200 times magnification. Microstructure examination reveals U3Si2 particles with diverse forms and sizes, Al matrix and AlMg2 cladding were spread along the U3Si2/Al side. Microstructure observation of irradiated U3Si2/Al has not shown good result because only topography observation of U3Si2/Al meat, Al matrix and AlMg2 cladding can be done due to limited capability of the optical microscope in hot cell, where maximum magnification can be attained only at 200 times so that the phenomenon of interaction layer and small gas bubble cannot be observed. However, U3Si2/Al microstructure of 56% burnup, if compared to the microstructure of U3Si2/Al fuel element plate of 60% burnup from previous researcher, shows interaction between U3Si2 meat with Al matrix and the existence of layers with a thickness about 5 up to 20 microns. Meanwhile, the observed thickness of AlMg2 cladding is greater than 0.25 mm, which indicates that irradiation does not significantly change the thickness of AlMg2 cladding so that the overall irradiated U3Si2-Al still has good integrity and stability.

PEMISAHAN CESIUM DALAM BAHAN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 BURN UP 60% POTONGAN BOTTOM Ariyanti Saputri; Sutri Indaryati; Iis Haryati; Yanlinastuti Yanlinastuti; Hanifah Rifaatul Mahmudah; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 3 (2021): 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.2021.27.3.6571

The separation of cesium in U3Si2/Al fuel with a density of 4.8 gU/cm3 and 60% burn up by cation exchange using zeolite from Lampung has been carried out. Cesium isotope is used as a burn-up indicator for irradiated nuclear fuel. The separation aims to obtain an accurate cesium weight so that the calculation of burn up by the destructive method can be carried out correctly. The fuel plate of U3Si2/Al was cut in duplicates at the bottom with a weight of B-1=0.036 g and B-2= 0.037g, respectively. The fuel plate of U3Si2/Al with this weight was then dissolved using 6N HCl and 6N HNO3 in 10 mL. The solution of U3Si2/Al was then pipetted 1 mL and transferred from the hot cell to R.135 and diluted to 25 mL. The solution was pipetted 50 µL into a vial in duplicates and 1000 mg of Lampung zeolite was added. Separation process of 134Cs and 137Cs from 235U was done by cation exchange for 60 minutes. The results obtained were isotopes 134Cs and 137Cs in the solid phase while uranium (238U, 235U, 234U) and other isotopes in the liquid phase. The weight of the isotopes of 134Cs and 137Cs was then measured using a spectrometer/g. The weight of the isotopes of 137Cs and 134Cs in solution at Bottom position was B-1=0.00003283 g/0.036g and B-1= 0.000000147 g/0.036 g for 137Cs and 134Cs respectively while another duplicate was B-2=0.00003290 g/0.037g for 137Cs and B-2=0.000000222 g/0.037g for 134Cs. It can be concluded that in the separation of cesium in 50 µL solution of U3Si2/Al at Bottom position by cation exchange using 1000 mg of zeolite from Lampung, good results were obtained.

PENGARUH PENAMBAHAN ION SULFAT TERHADAP REKOVERI PEMISAHAN URANIUM MENGGUNAKAN METODE KOLOM PENUKAR ANION Boybul Boybul; Yanlinastuti Yanlinastuti; Dian Anggraini; Aslina Br. Ginting; Arif Nugroho; Rosika Kriswarini
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.2017.23.3.3679

In the previous research, it was observed that the recovery of uranium separation by anion exchange column method with HCl 12 N solvent was 68.2137 %. The recovery can be increased by optimizing the uranium separation parameters by the use of HCl and Na2SO4 solvent mixture. A 500 μL uranyl nitrate standard solution was used as feed with varied HCl concentration of 6 N, 9 N, 12 N and varied Na2SO4 concentration of 500, 1000, 1500, 2000, 2500 and 3500 ppm as reagent solution. In the anion exchange process, uranium was bound by the resin to form [UO2(SO4)3]4- and [UO2(SO4)2]2 complex compounds, and these complexes were eluted with 15 mL of 0.15 N HCl dilute solution. The eluate was heated to nearly dried condition and 1 mL of HCl concentrated solution was added for electrodeposition process. The uranium deposited on stainless steel planset, as the result of electrodeposition process, was analyzed with alpha spectrometer. It was observed that the largest 235U content was found in 9M of HCl solvent and 1500 ppm of Na2SO4 with 95.7124 % recovery. Therefore, the concentration value of HCl of 9 N and 1500 ppm of Na2SO4 were subsequently applied to the uranium separation of irradiated U3Si2/Al fuel element plate. An amount of 500 μL supernatant of U3Si2/Al specimen taken from the top, middle and bottom position of fuel element plate (FEP) were put into an anion exchange column containing 1 g of Dowex-Cl resin. The results of the separation process were 235U isotope identified according to their position in the irradiated U3Si2/Al fuel element plate i.e. top, middle, and bottom. It was found that the recovery values were 13265.7866 μg/gFEP; 6923.9248 μg/gFEP; and 12332.4175 μg/gFEP representing their position of top, middle and bottom respectively. It is concluded that the use of 9M of HCl solvent and 1500 ppm of Na2SO4 by anion exchange column method can improve uranium separation recovery from 68.2137 % to 95.7124 %.

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