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All Journal Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Ariyanti Saputri
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Materials Science & Nanotechnology

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OPTIMASI PARAMETER METODE PEMISAHAN RADIONUKLIDA 95Zr DALAM LARUTAN PELAT ELEMEN BAKAR U3Si2/Al TERIRADIASI Yanlinastuti Yanlinastuti; Noviarty Noviarty; Iis Haryati; Ariyanti Saputri; Boybul Boybul; Supardjo Supardjo; Erlina Noerpitasari; 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.2021.27.3.6535

Abstract

OPTIMASI PARAMETER METODE PEMISAHAN RADIONUKLIDA 95Zr  DALAM  LARUTAN PELAT ELEMEN BAKAR U3Si2/Al TERIRADIASI. Radionuklida 95Zr adalah salah satu radionuklida hasil belah pemancar radiasi-γ dan berumur paruh pendek sehingga dapat digunakan sebagai indikator burn up. Dalam pelat elemen bakar U3Si2/Al teriradiasi terdapat beberapa radionuklida hasil belah yang memancarkan radiasi α, β dan γ sehingga pada saat pengukuran menggunakan spektrometri-γ, radionuklida ini saling mengganggu mengakibatkan hasil pengukuran tidak akurat. Oleh sebab itu, perlu dilakukan pemisahan 95Zr sehingga pada saat pengukuran dengan spektrometer-γ diperoleh hasil yang akurat. Tujuan penelitian ini untuk mendapatkan parameter yang optimum terhadap pemisahan 95Zr dalam larutan pelat elemen bakar U3Si2/Al densitas 4,8 gU/cm3 teriradiasi dengan metode kolom penukar ion menggunakan resin Dowex 1x-8Cl- diameter 100-200 mesh. Parameter optimum yang diperoleh selanjutnya digunakan untuk pemisahan 95Zr dalam larutan pelat elemen bakar U3Si2/Al densitas 4,8 gU/cm3 teriradiasi. Dari hasil penelitian diperoleh parameter optimum keasaman H2SO4 pada umpan dengan konsentrasi 0,5 M, keasaman H2SO4 untuk elusi konsentrasi 1,0 M dengan recovery 98,20%. Berat resin untuk mengikat radionuklida 95Zr sebanyak 2,0 g dengan recovery 78,76%; volum umpan yang dibutuhkan sebanyak 50 µL dengan recovery 96,90% dan kecepatan alir  sebesar 0,1 mL/menit dengan recovery  96,72%. Parameter optimum tersebut digunakan untuk pemisahan larutan pelat elemen bakar U3Si2/Al densitas 4,8 gU/cm3 teriradiasi dengan kode Bottom (B), Middle (M) dan Top (T). Hasil pengukuran didapat rerata recovery pemisahan 95Zr masing-masing untuk kode B-1= 75,078%; B-2= 81,401%; M1=76,850%; M-2=83,806%; T-1=84,433%; dan T-2=81,728% dengan keberterimaan nilai CV repeatability lebih kecil dibandingkan dengan nilai CV Horwitz.  Kata kunci: kolom penukar ion, U3Si2/Al teriradiasi, radionuklida 95Zr,  spektrometer-γ, uji Horwitz.
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

Abstract

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 METODE PEMISAHAN RADIONUKLIDA 95Zr DALAM LARUTAN PELAT ELEMEN BAKAR U3Si2/Al TERIRADIASI Yanlinastuti Yanlinastuti; Noviarty Noviarty; Iis Haryati; Ariyanti Saputri; Boybul Boybul; Supardjo
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.2021.27.3.6535

Abstract

Radionuclide of 95Zr is one of the γ-radiation emitter radionuclides which has a short half-life so that it can be used as an indicator of burn up. In the irradiated U3Si2/Al fuel element plate there are several radionuclides of fission products emitting α, β and γ and when measuring radiation using γ-spectrometry, these radionuclides may interfere with each other resulting in inaccurate measurement results. Therefore, it is necessary to separate 95Zr for better accuracy in the measurement of γ-radiation with a γ-spectrometer. The purpose of this study was to obtain the optimum parameters for the separation of 95Zr in U3Si2/Al fuel element plate solution by ion exchange column method using Dowex 1x-8Cl- resin of 100-200 mesh in diameter. The optimum parameters obtained were then used for the separation of 95Zr in a solution of irradiated U3Si2/Al fuel element. It was found that the optimum parameter of acidity of H2SO4 in the feed was a concentration of 0.5 M, and the acidity of H2SO4 for elution was 1.0 M with a recovery of 98.20%. The weight of the resin to bind 95Zr radionuclide was 2.0 g with a recovery of 78.76%. The required feed volume was 50 µL with a recovery of 96.90% and the optimized flow rate was 0.1 mL/minute with a recovery of 96.72%. The optimum values were used for the separation of the U3Si2/Al fuel element plate solution irradiated with the code of Bottom (B), Middle (M) and Top (T). The measurement results show that the mean recovery of separation was 95Zr for code B-1 = 75.078%; B-2= 81.401%; M1=76,850%; M-2=83.806%; T-1=84.433%; and T-2 = 81.728% with the acceptability of the CV repeatability value smaller than the CV Horwitz value.
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

Abstract

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.
KARAKTERISASI TERMAL PEB U-7Mo/Al SEBAGAI BAHAN BAKAR REAKTOR RISET Sayyidatun Nisa; Ariyanti Saputri; Sutri Indaryati; Noviarty Noviarty; Supardjo; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 27 No. 2 (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.2021.27.2.6420

Abstract

UMo/Al-based fuel is a candidate for research reactor fuel and as an alternative to U3Si2/Al fuel. This is because the UMo/Al alloy has a higher uranium density of 16.4 g/cm3 compared to U3Si2/Al of 12.2 g/cm3. In addition, the UMo alloy has a low neutron absorption cross section and its reprocessing process is relatively easy. The U-7Mo/Al alloy is able to maintain the γ-U phase during irradiation process so that the stability of the fuel in the reactor is maintained. The U-7Mo alloy has been fabricated into a U-7Mo/Al mini fuel element plate. The purpose of this study was to determine the thermal characteristics of U-7Mo/Al as inputs to the research reactor fuel fabricator in the manufacture of UMo/Al-based fuel. Thermal characterization was carried out for uranium, molybdenum, UMo and the fuel element plate of U-7Mo/Al using Differential Scanning Calorimetry (DSC). The thermal characterization results show that the U-7Mo/Al fuel element plate is thermally stable up to 600 °C because it undergoes an endothermic thermochemical reaction at a temperature of 632.962 °C with DH = 144.318 J/g. At 656.186 °C, the Al matrix and AlMg2 cladding are fused in the U-7Mo/Al with DH = 144.318 J/g. At temperatures of 952.810 °C to 1106.050 °C, the molten Al matrix diffuses with UMo to form a metastable U(Mo,Al)X compound and heating to a temperature of 1211.760 °C forms a UAlX layer (UAl2, UAl3 and UAl4) with DH = –22,721 J/g.
Co-Authors ASLINA BR. GINTING BOYBUL BOYBUL Erlina Noerpitasari Hanifah Rifaatul Mahmudah Iis Haryati Noviarty Noviarty Sayyidatun Nisa Supardjo Supardjo Supardjo Sutri Indaryati Yanlinastuti Yanlinastuti Yanlinastuti Yanlinastuti