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

Sari

Abstract

Absolut burn-up determination of U₃Si₂-Al irradiated fuel plate with loading 2.96 gU/cm³. Absolute burn up measurement of U₃Si₂-Al irradiated fuel element with loading of 2.96 gU/cm³with  RI-SIE 2 code has been done. The burn up calculation of U₃Si₂-Al irradiated fuel element is based on the content of ¹³⁷ Cs, ²³⁵U 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  ²³⁵U isotope accurately.Separation and analysis of ¹³⁷Cs isotope had been done by cation exchange using zeolit Lampung and spectrometre-g. While the separation both of isotop ²³⁵U and ²³⁹Pu 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 HNO₃ 8N and the efluent of Pu was eluted by HCl 0.1N + HF 0.036N. Both of isotopes were analyzed by using a spectrometre-a. The analysis result showed that the content of ¹³⁷Cs isotope in U₃Si₂-Al irradiated fuel element was 0.000716 g/g sample, while the content of ²³⁵U, ²³⁹ Pu and ²³⁸ Pu were 0.032824 g/g sample, 0.000011g/g sample and 0.000005 g/g sample respectively. The result of measurement ²³⁵U isotope compared with initially content of isotop ²³⁵U (fabrication data) for being used in the absolute burn up measurement. The result of absolute burn up calculation of U₃Si₂-Al irradiated fuel U₃Si₂-Al with loading of 2.96 gU/cm³with RI-SIE 2 code was 51.69 %.

Keyword : Separation and analysis of isotopes (Cs, U, Pu), cation and anion exchange, U₃Si₂-Al irradiated fuel element, burn up..

Abstrak

Penentuan burn up mutlak  pelat elemen bakar U₃Si₂-Al tingkat muat uranium  2,96 gU/cm³pasca iradiasi. Telah dilakukan perhitungan burn up mutlak bahan bakar PEB U₃Si₂-Al tingkat muat uranium (TMU) 2,96 gU/cm³ pasca iradiasi dengan kode RI-SIE 2. Perhitungan dilakukan melalui hasilpemisahan dan analisis isotop ¹³⁷Cs isotop,²³⁵U,dan Pu di dalam PEB U₃Si₂-Al pasca iradiasi secara radiokimia. Tujuan pemisahan isotop hasil fisi khususnya isotop ¹³⁷Cs dengan  unsur heavy element (uranium dan plutonium) adalah untuk mendapatkan kandungan isotop ²³⁵U sisa (tidak terbakar) secara akurat. Pemungutan isotop ¹³⁷Cs dilakukan dengan metode penukar kation menggunakan zeolit Lampung dan analisisnya menggunakan spektrometer-g, sedangkan pemungutan isotop ²³⁵U dan ²³⁹Pu dilakukan dengan metode kolom penukar anion menggunakan resin Dowex 1x8. Efluen U di dalam kolom dielusi menggunakan HNO₃ 8N dan efluen Pu dielusi dengan HCl 0,1N+HF 0,036N dan dianalisis menggunakan spektrometer-α.Hasil analisis menunjukkan bahwa kandungan isotop ¹³⁷Cs di dalam PEB U₃Si₂-Al pasca iradiasi diperoleh sebesar 0,000716 g/g sampel, sedangkan kandungan isotop U dan Pu diperoleh masing-masing sebesar²³⁵U= 0,032824 g/g sampel, ²³⁹Pu= 0,000011g/g sampel dan ²³⁸Pu=0,000005 g/g sampel. Kandungan isotop ²³⁵U hasil pengukuran selanjutnya dibandingkan dengan kandungan isotop ²³⁵U mula-mula (data pabrikasi) untuk digunakan dalam perhitungan burn up mutlak. Hasil perhitungan burn up mutlak bahan bakar PEB U₃Si₂-Al TMU 2,96 gU/cm³ 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 U₃Si₂-Al pasca  iradiasi, burn up.