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All Journal Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Rosika Kriswarini
Pusat Teknologi Bahan Bakar Nuklir – BATAN

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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

Abstract

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.
PROSES ELEKTRODEPOSISI UNTUK PENGUKURAN ISOTOP 242Pu DENGAN SPEKTROMETER ALPHA Boybul Boybul; Yanlinastuti Yanlinastuti; Arif Nugroho; Rosika Kriswarini; Aslina Br. Ginting
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.2020.26.3.6071

Abstract

OPTIMIZATION OF ELECTRODEPOSITION PROCESS FOR 242Pu MEASUREMENT BY ALPHA SPECTROMETRY. In this study electrodeposition method was used to design and set up an electrodeposition device for 242Pu source preparation for measurement by alpha spectrometry. The purpose of this study was to determine the optimal electrodeposition process parameters so as to obtain 242Pu alpha sources with good spectrum properties and maximum result from source preparation by electrodeposition process. Standard samples of 242Pu with specific activity were prepared from plutonium standard aqueous solution. Experiments were conducted to determine the main parameters that have significant influence on the deposition efficiency. The electrodeposition process parameters analyzed were the effects of time, electric current and anode-cathode distance using an electrolyte solution of ammonium sulphate at pH 3.5. The results of the optimization of the electrodeposition process were optimal time of 2.5 hours, electric current of 1.4A and cathode- anode distance of 10 mm. These parameters' values are the best conditions for the deposition of 242Pu. Alpha measurement results of the electrodeposited source of 242Pu also show good spectrawith electrodeposition process reproductibility of 95.3%.
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

Abstract

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.
Co-Authors Agus Jamaludin Arif Nugroho Aslina Br. Ginting Boybul Boybul Erlina Noerpitasari Iis Haryati Noviarty Noviarty Samsul Fatimah Sayyidatun Nisa Sutri Indaryati Yanlinastuti Yanlinastuti