Penentuan burn up mutlak pelat elmen bakar U3Si2-Al tingkat muat uranium 2,96 gU/cm3pasca iradiasi

Abstract Absolut burn-up determination of U 3 Si 2 -Al irradiated fuel plate with loading 2.96 gU/cm 3 . A bsolute burn up measurement of U 3 Si 2 -Al irradiated fuel element with loading of 2.96 gU/cm 3 with RI-SIE 2 code has been done. The burn up calculation of U 3 Si 2 -Al irradiated fuel element is based on the content of 137 Cs, 235 U and 239 Pu isotopes which is obtained by radiochemical analysis after an appropriate separation. The purpose of the separation a monitoring of the fission product ( 137 Cs isotope) and the heavy elements (uranium and plutonium) is to get the amount of 235 U isotope accurately.Separation and analysis of 137 Cs isotope had been done by cation exchange using z eolit Lampung and spe c trometre- g . W hile the separation both of isotop 235 U and 239 Pu had been done by anion exchange column using Dowex 1 x 8 resin. The efluen of U in the column anion exchanger was eluted by using HNO 3 8N and the efluent of Pu was eluted by HCl 0.1N + HF 0. 036 N. Both of isotopes were analyzed by using a spectrometre- a . The analysis result showed that the content of 137 Cs isotop e in U 3 Si 2 -Al irradiated fuel element was 0.000 716 g/g sample, while the content of 235 U , 239 Pu and 238 Pu were 0 . 032824 g/g sample, 0 . 000011 g/g sample and 0 . 000005 g/g sample respectively. The result of measurement 235 U isotop e compared with initially content of isotop 235 U ( fabrication data) for being used in the absolute burn up measurement. The result of absolute burn up calculation of U 3 Si 2 -Al irradiated fuel U 3 Si 2 -Al with loading of 2.96 gU/cm 3 with RI-SIE 2 code was 5 1 . 69 %. Keyword : Separation and a nalysis of isotopes (C s , U, Pu), c ation and anion exchange , U 3 Si 2 -Al irradiated fuel element , burn up.. Abstrak Penentuan burn up mutlak pelat elemen bakar U 3 Si 2 -Al tingkat muat uranium 2,96 gU/cm 3 pasca iradiasi. Telah dilakukan perhitungan burn up mutlak bahan bakar PEB U 3 Si 2 -Al tingkat muat uranium (TMU) 2,96 gU/cm 3 pasca iradiasi dengan kode RI-SIE 2. Perhitungan dilakukan melalui hasilpemisahan dan analisis isotop 137 Cs isotop, 235 U,dan Pu di dalam PEB U 3 Si 2 -Al pasca iradiasi secara radiokimia. Tujuan pemisahan isotop hasil fisi khususnya isotop 137 Cs dengan unsur heavy element (uranium dan plutonium) adalah untuk mendapatkan kandungan isotop 235 U sisa (tidak terbakar) secara akurat. Pemungutan isotop 137 Cs dilakukan dengan metode penukar kation menggunakan zeolit Lampung dan analisisnya menggunakan spektrometer-g, sedangkan pemungutan isotop 235 U dan 239 Pu dilakukan dengan metode kolom penukar anion menggunakan resin Dowex 1x8. Efluen U di dalam kolom dielusi menggunakan HNO 3 8N dan efluen Pu dielusi dengan HCl 0,1N+HF 0,036N dan dianalisis menggunakan spektrometer-α.Hasil analisis menunjukkan bahwa kandungan isotop 137 Cs di dalam PEB U 3 Si 2 -Al pasca iradiasi diperoleh sebesar 0,000716 g/g sampel, sedangkan kandungan isotop U dan Pu diperoleh masing-masing sebesar 235 U= 0,032824 g/g sampel, 239 Pu= 0,000011g/g sampel dan 238 Pu=0,000005 g/g sampel. Kandungan isotop 235 U hasil pengukuran selanjutnya dibandingkan dengan kandungan isotop 235 U mula-mula (data pabrikasi) untuk digunakan dalam perhitungan burn up mutlak. Hasil perhitungan burn up mutlak bahan bakar PEB U 3 Si 2 -Al TMU 2,96 gU/cm 3 pasca iradiasi dengan kode RI-SIE 2 diperoleh sebesar 51,69 %. Kata kunci : Pemisahan dan analisis isotop (Cs, U, Pu), penukar kation dan anion, PEB U 3 Si 2 -Al pasca iradiasi, burn up .