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PENENTUAN RECOVERY NEODYMIUM DAN CERIUM PADA PROSES PEMISAHAN ISOTOP DARI SIMULASI PEB U3Si2/Al PRA IRADIASI Noviarty Noviarty; Erlina Noerpitasari; Rosika Kriswarini; Agus Jamaludin; Sutri Indaryati; Sayyidatun Nisa; Samsul Fatimah
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 1 (2020): 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.2020.26.1.5791

DETERMINATION OF NEODYMIUM AND CERIUM RECOVERY IN ISOTOPE SEPARATION PROCESS OF SIMULATED PRE-IRADIATED U3Si2/Al FUEL. Neodymium (Nd) is one of the fission product isotopes used as an indicator of nuclear fuel burn-up because Nd isotope is a stable fission product, has a sufficiently great yield, is not volatile and has low neutron-capture cross- section. Burn-up determination using Nd can support and verify the results of the burn-up determined by using Cs, U and Pu isotopes. Destructive burn-up determination (Destructive Test, DT) is based on the determination of specific isotopes that is performed physicochemically using mass spectrometer equipment. Based on ASTM E 321-69 method for Nd isotope analysis, Nd separation from Ce is required because 142Ce isotope interferes with 142Nd measurement due to their being isobars, and this phenomenon will affect the results of the burn-up calculations. In addition, Nd isotope in U3Si2/Al fuel is present along with other fission isotopes such as 235U, 239Pu, 148Nd, 137Cs, 152Eu, 90Sr, 143Ce, 103Ru, 95Zr, and 95Nb. Therefore, to obtain an accurate value to be used as burn-up indicator, the isotopes must be separated. Before the Nd and Ce separation, several separation phases of Cs isotopes (137Cs, 134Cs), U isotopes (234U, 235U, 236U, 238U), Pu isotopes (239Pu, 238Pu) and other isotopes (152Eu, 90Sr, 103Ru, 95Zr and 95Nb) were done. The determination of separation recovery aimed to determine the amount of Nd and Ce at each stage of the separation process of other isotopes prior to the separation stage of Nd and Ce. The determination of recovery was conducted by a simulation of fresh U3Si2/Al solution plus standard solutions of Cs, U, Nd and Ce. The recovery for Nd and Ce from Cs separation phase using zeolites were 69.91% and 64.42% respectively while the recovery of Nd and Ce at Pu and U separation phase were close to 100%. The recovery values of Nd and Ce were then used as a correction in the calculation of Nd and Ce separation from the fuel solution, and the corrected values can then be used as a reference in determining the burn-up of U3Si2/Al fuel using Nd as an indicator.

PERHITUNGAN BURN UP PEB U3Si2/Al DENSITAS 4,8 gU/cm3 PASCA IRADIASI POTONGAN BAGIAN MIDDLE Aslina Br. Ginting; Supardjo Supardjo; Yanlinastuti Yanlinastuti; Sutri Indaryati; Boybul Boybul
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 2 (2020): 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.2020.26.2.5864

BURN UP CALCULATION OF THE MIDDLE PART OF IRRADIATED U3Si2/Al FUEL PLATE WITH 4.8 gU/cm3 DENSITY. Post-irradiation examination with non-destructive and destructive methods is required to study the performance of U3Si2/Al fuel during irradiation at the G. A. Siwabessy Multipurpose Reactor (RSG-GAS). The purpose of the burn-up calculation is to discover the 235U content that burned in a fuel plate of U3Si2/Al during use in RSG-GAS and to prove the burn-up obtained using destructive method by calculation using Origen Code. Therefore, this research performed a burn-up calculation of U3Si2/Al fuel plate (with a density of 4.8 gU/cm3) using destructive method through physicochemical analysis. The physicochemical analysis was aimed to determine the isotope content of 235U, 134Cs, and 137Cs in the irradiated U3Si2/Al fuel plate. The fuel plate was cut at the middle using a diamond cutting machine in a hot cell to obtain a sample cut with a weight of M-1 = 0.056 g, and a duplicate cut was also prepared with a weight of M-2 = 0.075 g. The sample was then dissolved using HCl 6 N and HNO3 6N. The results of dissolution was UO2(NO3)2 solution containing isotopic fission such as cesium and uranium. The solution of UO2(NO3)2 was pipetted at 1 mL and then transferred from the hot cell to R.135 (outside the hot cell) to separate 134Cs and 137Cs from 235U by a cation exchange method using zeolite from Lampung. The solution of UO2(NO3)2 was pipetted at 100 µL into a vial in duplicates and then 1000 mg zeolite was added. The cation exchange process was then carried out by stirring for 1 h. The separation process resulted in 134Cs and 137Cs isotopes in the solid phase, while uranium isotopes (238U, 235U, 234U), plutonium (239Pu, 238Pu) and other isotopes were in the liquid phase. Separation of uranium from other isotopes was done by anion exchange column method using 1200 mg of Dowex resin. The isotope content of 235U, 134Cs, 137Cs, 239Pu, and 238Pu was then measured using α/- spectrometer, the values of which were subsequently used for burn-up calculation. The result of the burn up calculation is 41.6565 ± 1.687%. The value of burn-up is not significantly different from the burn-up obtained from the calculation using Origen Code, which is 40%.

PENENTUAN BERAT ISOTOP CESIUM DAN URANIUM DALAM PELAT ELEMEN BAKAR U3Si2/Al DENSITAS 4,8 gU/cm3 Yanlinastut Yanlinastut; Sutri Indaryati; Boybul Boybul; Supardjo Supardjo; Aslina Br. Ginting
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 2 (2020): 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.2020.26.2.5874

DETERMINATION OF WEIGHT OF CESIUM AND URANIUM ISOTOPES IN IRRADIATED U3Si2/Al FUEL PLATE WITH 4.8 gU/cm3 DENSITY AND 40% BURN UP. The fuel plate of U3Si2/Al with a density of 4.8 gU/cm3 was irradiated in the RSG-GAS multipurpose reactor with 40% burn- up. During irradiation, the amount of isotopes produced by fission reaction, such as cesium, uranium and other isotopes can be used for burn-up calculation to determine the fuel performance. Physicochemical analysis was performed to determine the weight of cesium and uranium isotopes in the irradiated fuel. The irradiated plate of U3Si2/Al was cut at the middle section (duplo) with a weight of M-1 = 0.065 g and M-2 = 0.075 g and dissolved in HCl 6N and HNO3 6N. The resulted was pipetted at 100 µL and then added into each of 2 mL solvent of HNO3, H2SO4 and HCl 0.1N. The separation of cesium was then carried out with the addition 1000 mg of zeolite from Lampung. Cesium isotope obtained from the separation was bound with zeolite in the solid phase while uranium was in the liquid phase. Cesium isotopes in the solid phase and in the liquid phase were measured by a spectrometer- for their radioactivity for 10000 seconds. The measurement was indicated by spectra of 134Cs at 604.7 and 795.8keV energy and 137Cs at 661.7keV. Meanwhile, the separation of uranium in the liquid phase was carried out using anion exchange column method with the addition of Dowex resin. The results of the separation were indicated by some spectra of U isotopes at various energies, 238U at 4,1943 MeV, 235U at 4,397 MeV, 236U at 4,494 MeV and 234U at 4,777 MeV. Weight calculation from the measurement data shows that the weight of 137Cs in 0.056 g of the irradiated U3Si2/Al fuel samples in HNO3, H2SO4 and HCl solvent are 4.08E-05 g; 4.53E-05 g ,and 4.53E-05 g respectively, while 134Cs weight are 4,84E-08 g; 5,30E-08 g and 5,20E-08 g respectively. Meanwhile, 137Cs isotope weight in 0.075 g fuel plate of U3Si2/Al are obtained by 5.93E-07 g; 5.90-05 g, and 5.88E-05 g, while the isotope weight of 134Cs in HNO3, H2SO4 and HCl solvent are 5,23E-07 g; 5,29E-07g and 5,008E-07g respectively. The isotopes weight of 238U, 235U, 236U and 234U in 0.056 g of fuel plale are 6.45E-03 g; 2.57E-03 g; 2.42E-06 g; and 1.90E-05 g, and the weight in 0.075 g fuel plale are 7.41E-03 g; 2.40E-03 g; 2.91E-06 g; and 2.17E-05 g. The isotopes weight of 134Cs, 137Cs, 238U, 235U, 236U and 234U in 0.056 g and 0.075 irradiated U3Si2/Al fuel plate obtained were relatively similarly. Data of isotopes weight are then used as input data for burn up calculation.

ANALISIS ISOTOP 137Cs DALAM PEB U3Si2/Al DENSITAS 4,8 gU/cm3 PASCA IRADIASI DENGAN METODE PENGENDAPAN CHLOROPLATINATE DAN KOLOM PENUKAR KATION RESIN DOWEX Arif Nugroho; Boybul Boybul; Sutri Indaryati; Iis Haryati; Rosika Kriswarini; Erlina Noerpitasari
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 26 No. 3 (2020): 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.2020.26.3.6055

SEPARATION OF CESIUM IN IRRADIATED U3Si2/Al FUEL PLATE WITH A DENSITY OF 4.8 gU/cm3 USING CHLOROPLATINATE DEPOSITION METHOD AND DOWEX RESIN CATION EXCHANGE COLUMN. Dissolution of the U3Si2/Al plate was carried out in hot cell 109 using 6 M HCl and 6 M HNO3 solutions. The separation of cesium and uranium in uranyl nitrate solution was carried out using chloroplatinate deposition method and a cation exchange column. In the chloroplatinate deposition, the process of removing elements that will interfere with the deposition process was performed first, then the separation of heavy elements such as uranium or plutonium was carried out by depositing the 137Cs in the form of Cs2PtCl6. The isotope content of 137Cs in the Cs2PtCl6 deposition was measured with a γ spectrometer. In the Dowex resin cation exchange column method, the uranyl nitrate solution was pipetted 150 μL to be added to 2 mL of aquadest. To this solution was then added 20 μL of Cs carrier and 1 mL of 12 M HCl. The mixture of the solution was used as feed and put into the anion exchange column containing R-Cl resin. The effluent exiting the anion exchange column was fed into the cation exchange column containing R- NH4+ resin. The 137Cs isotope bound to R NH4+ resin in the column was then eluted using 1 M HCI. The effluent was compressed until a volume of ± 2 mL was obtained. The isotope content of 137Cs in U3Si2 / Al plate obtained as a result of separation using the chloroplatinate method for middle slices coded M has an average of 0.000557 g/g fuel and 0.000652 g/g fuel for the bottom slices coded B, while the Dowex resin cation exchange column method gave an average of 0.000747 g/g fuel for middle slices coded M, and 0.000934 g/g fuel for bottom slices coded B. The recovery of 137Cs separation by the anion exchange column method was greater than that of the Cs2PtCl6 deposition method.

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