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All Journal Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Yanlinastuti Yanlinastuti
Pusat Teknologi Bahan Bakar Nuklir - BATAN
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.
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
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2020.26.2.5874

Abstract

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.
PEMBUATAN SERBUK U-6Zr DENGAN PENGKAYAAN URANIUM 19,75 % UNTUK BAHAN BAKAR REAKTOR RISET Masrukan Masrukan; Sungkono Sungkono; Yanlinastuti Yanlinastuti; Tri Yulianto; Ridwan Ridwan
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 3 (2015): 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.2015.21.3.2460

Abstract

Making U-6Zr alloy powder with enrichment of 19.75 % for a research reactor fuel has been done. Making of U-6Zr fuel in order to find new fuels that have a high density to replace the existing fuel U3Si2-Al. The purpose of this experiment was to determine the properties of U-6Zr alloy powder obtained from the hydriding-dehydriding process as a candidate research reactor fuel. Initially was made U-6Zr ingot by melting U and Zr metals using electric arc melting furnace. U-6Zr ingots were found then cut into pieces and put into hydriding-dehydriding equipment that operates at pressures 14,46054 psi and hydriding temperatures of 350 oC. Ingots that out of the hydriding-dehydriding equipment becomes brittle then was crushed so becomes powder. Powder that obtained subjected to the test, including chemical composition testing, density, hydrogen content, phase and thermal properties. The results testing show that chemical composition of some elements such as Al, Ca, Cu, and Ni exceeded the permitted limit, each of which contained elements of 202.21 ppm, 214.05 ppm, 61.25 ppm, and 134.53 ppm. On testing the density obtained that U-6Zr powder density of 13.57 g/cc and the testing of hydrogen residual content obtained hydrogen residual content of 0.16 %. For the testing phase were obtained the αU and δU phases, while in testing of the transformation temperature, there are two peaks, the first peak occurs at a temperature of 274 to 311 °C and a second peak occurs at a temperature of 493 to 527 oC. The first peak occurs endothermic reaction by absorbing heat of 6.23 cal/g but not formed a new phase, while the second peak occurs exothermic reaction with brought out heat of -9.34 cal/g and formed αZr phase. Meanwhile, the heat capacity of the test at temperature of 34 to 75 °C, the decrease in the value of the heat capacity accompanied heat absorption. At higher temperatures up to 437 °C, heat capacity value becomes negative and accompanied by heat expenditure. It can be concluded that the alloy the U-6Zr when viewed from the chemical composition can still be used for fuel research reactor. Residual hydrogen still found in small quantities in the U-6Zr powder that can be eliminated by heating for longer. Reaction between Zr with residual hydrogen to form the αZ phase is accompanied exothermic reaction with brought out heat of 93 449 cal/g.
PENENTUAN KANDUNGAN ISOTOP 235U DALAM PEB U3Si2-Al TMU 2,96 gU/cm3 UNTUK PERHITUNGAN BURN-UP Boybul Boybul; Yanlinastuti Yanlinastuti; Sutri Indaryati; Iis Haryati; Arif Nugroho
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 3 (2015): 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.2015.21.3.2464

Abstract

235U separation has been carried out in the solution of PEB U3Si2 - Al with loading of uranium (TMU) 2.96 gU/cm3 at the Top. Top of PEB U3Si2-Al cut into three sections (triplo) with code T1, T2 and T3. Weight of each PEB code T1 = 0.095 g, T2 = 0.086 g and T3 = 0.087 g and dissolved using HCl and HNO3 in hotcell. The purpose of this study was to determine the content of the isotope 235U in the solution PEB U3Si2-Al post-irradiation and subsequently used for the calculation of burn-up. 235U isotope separation in the solution PEB U3Si2 - Al was conducted using an anion exchange column method using Dowex1x8 resin. Pipette solution of 100 mL, and then put into a column containing Dowex resin with a weight of 1.2 g. U effluent results in the column was eluted using 0.1 M HCl, then dried and conducted electro-deposition process and then analyzed using a spectrometer-α. The analysis showed that the content of the isotope 235U obtained at T1 = 0.03665 g/g PEB, T2 = 0.003468 g/g PEB and T3 = 0.03208 g/g PEB with separation recovery of 63.71 %. The content of isotope 235U obtained is used for the calculation of burn-up. burn-up calculation results of PEB U3Si2-Al of Top section (T1, T2 and T3) were obtained respectively by 43.31 %, 49.48 % and 45.41 % or burn-up an average of 45.75 %. This data is smaller than a data burn-up of PEB U3Si2-Al of middle section of 50.69 % conducted by previous researchers. However, this data can not be used as an input to the reactor, due to should be equipped with a data burn-up of PEB U3Si2-Al of bottom section. Therefore, in the nextstudies will be conducted calculation of burn-up PEB U3Si2-Al of bottom section.
FENOMENA KOROSI ZIRKALOY-2 DAN ZIRKALOY-4 DALAM MEDIA LARUTAN NaCl SECARA ELEKTROKIMIA Dian Anggraini; Maman Kartaman Ajiriyanto; Rosika Kriswarini; Yanlinastuti Yanlinastuti
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 21 No. 3 (2015): 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.2015.21.3.2465

Abstract

Zircaloy-2 and zircaloy-4 are used as cladding material in Light Water Reactor, (LWR), Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR). During its use in the spent fuel pool may interact between the cladding and seawater in case of abnormal condition. Chloride ion which contained in seawater has the potential for being corrosion in cladding material. The aim of this work was knowing zircaloy-2 and zircaloy-4 corrosion phenomena in NaCl medium by corrosion parameter determination with polarization resistance technique, tafel, and potentiodynamic. Samples are zircaloy-2 and zircaloy-4 pieces material with 1x1 cm dimension. The samples are mounting and soldered with copper wire, then the sample surface are polished by 1200 grade grinding paper. Corrosion test was done with corrosion cell that was completed by electrode standard (saturated calomel), electrode buffer (graphite) and work electrode (sample). Solvent medium was NaCl solution with concentration 3.5 %; 0.35 %; and 0.175 %. The result showed that ion Clˉ contained in NaCl which were concentration area from 0.175 % to 3.5 % did not affect corrosion mechanism. The corrosion type in potential range ± 250 mV to E­­corr was uniform corrosion in ZrO­2 oxide form. Zirkaloy-2 and zirkaloy-4 corrosion rate in 3.5 % NaCl concentration were obtained 6.39×10-3 and 7.40×10-3 mpy respectively. Corrosion phenomenon which was observed by potentiodynamic technique (± 1000 mV to Ecorr) showed that zirkaloy-2 and zirkaloy-4 underwent passivation and pitting corrosion. Pitting potential zirkaloy-2 and zirkaloy-4 were obtained -452.8 mV and -182.8 mV severally.
Co-Authors Arif Nugroho Ariyanti Saputri ASLINA BR. GINTING BOYBUL BOYBUL Boybul Boybul Dian Anggraini Erlina Noerpitasari Iis Haryati Iis Haryati Maman Kartaman Ajiriyanto Masrukan Masrukan Noviarty Noviarty Ridwan Ridwan Rosika Kriswarini Sungkono Sungkono Supardjo Supardjo Sutri Indaryati Sutri Indaryati Tri Yulianto