Graphite matrix in Pebble Bed Reactor (PBR) fuel has an important role not only as neutron moderator and structural material to protect nuclear fuel, but also as heat transfer media. Therefore, the graphite matrix must meet the criteria of physical and chemical properties specified for PBR fuel. This paper focuses on the purification of the Indonesian natural graphite by using hydrometallurgy method with acid treatments. The characteristic of the purified graphite was studied for its specification compliance as a candidate of fuel matrix for PBR type of High Temperature Gas Cooled Reactor (HTGR). Acid and acid mixtures such as HF, HNO3+H2SO4 and HF+HCl+H2SO4 were used for the purification process. Crystal structure examination by X-Ray Diffraction indicates that the graphite sample was 2H poly type with hexagonal crystal structure and lattice group of P 63 m c space group. It was observed that the graphite sample purified by HNO3+H2SO4 mixture had the closest resemblance to single crystalline graphite with a <d002> deviation of 0.94 when compared to perfect graphite crystal. The density of graphite decreases from 2.3273 g/cm3 (before acid treatment) to 2.1808; 2.2203 and 2.2752 g/cm3 after treatment with HF, HNO3+H2SO4 and HF+HCl+H2SO4, respectively. These results are close to the theoretical density value of 2.26 g/cm3. The surface area decreases from 10.346 m2/g to 6.177; 5.831 and 7.63 m2/g for the treated graphite with HF, HNO3+H2SO4 and HF+HCl+H2SO4 respectively. However, these values are still higher than that of nuclear grade graphite (i.e. between 4.80 and 5.55 m2/g). The average diameter size of graphite decreased from 29.65 μm (before treated acid) into 23.12 μm (after treated acid). The Indonesian natural graphite obtained from acid purification treatment is potential to be used as matrix material for PBR - HTGR fuel, but further treatment is necessary.

KARAKTERISASI KANDUNGAN URANIUM DAN UNSUR JEJAK PELET SINTER UO2 UNTUK FORENSIK NUKLIR. Forensik nuklir merupakan salah satu alat yang penting didalam keamanan nuklir terkait dengan penegakan hukum. Hal ini dikarenakan  keberadaan bahan nuklir dan  radioaktif memiliki potensi bahaya baik dari segi keselamatan, kesehatan hingga ancaman dalam keamanan nuklir.  Didalam  forensik nuklir, sidik jari adalah karakteristik bahan nuklir dan radioaktif  untuk memberi  informasi asal-usul suatu bahan nuklir sehingga diharapkan mempunyai data-data dari bahan nuklir dan radioaktif. Data-data diperoleh dari hasil  karakterisasi berupa pengujian baik  pengujian secara fisika ataupun kimia. Pengujian secara fisika seperti pengamatan visual, dimensi, fasa sedangkan secara kimia antara lain penentuan unsur bahan nuklir, penentuan konsentrasi unsur–unsur  dalam bahan nuklir. Dalam makalah ini telah dilakukan pengujian kandungan uranium dan unsur jejak dalam bahan nuklir pelet uranium oksida (UO2) dengan tujuan untuk sidik jari dalam mendukung forensik nuklir yang ada di PTBBN, BATAN. Pengujian kandungan uranium dilakukan secara titrasi potensiometri sedangkan pengujian unsur jejak selain uranium dengan metode spektrofotometri serapan atom. Hasil rerata pengujian kandungan uranium dalam bahan nuklir  dan radioaktif tersebut diperoleh antara  87% sampai 88% hal ini menginformasikan bahwa bahan tersebut adalah bahan nuklir UO2.  Hasil pengujian kandungan unsur jejak selain uranium dalam pengujian ini berbeda pengayaan maka kandungan unsur jejaknya berbeda pula, sehingga dapat menginformasikan tentang tingkat pengayaan uranium yang dimiliki oleh pellet UO2 tersebut. Data-data tersebut dapat digunakan sebagai sidik jari dalam forensik nuklir sehingga dapat membantu penyidik dalam indentifikasi pada forensik nuklir apabila terjadi penyelewengan atau penyalahgunaan dari jenis bahan nuklir tersebut.Kata kunci: Uranium, pelet sinter, sidik jari, forensik nuklir.

PURIFICATION OF INDONESIAN NATURAL GRAPHITE AS CANDIDATE FOR NUCLEAR FUEL MATRIX BY ACID LEACHING METHOD: CHEMICAL CHARACTERIZATION. Graphite matrix in Pebble Bed Reactor (PBR) – High Temperature Gas Cooled Reactor (HTGR) has an important role as heat transfer medium, neutron moderator and structural material to protect fuel. Thus, graphite matrix must fulfill chemical and physical characteristics for PBR-HTGR fuel. Indonesia has graphite sources in several regions that can potentially be purified. This research aimed to purify Indonesian natural graphite by several variation of acids and to perform chemical characterizations. Natural graphite from flotation process was purified by several variations of acid, i. e., hydrofluoric acid (HF), sulphuric acid + nitric acid (H2SO4 + HNO3) and hydrofluoric acid + hydrochloric acid + sulphuric acid (HF + HCl + H2SO4) and subsequently followed by chemical characterizations such as purity level, ash content, and boron quivalent. The highest purity was obtained in the purification process by HF with carbon content up to 99.52%; this purity level fulfills the specification of nuclear graphite (>99%). Ash content analysis shows a value in compliance with the specification requirement, i.e., < 100 ppm, and boron equivalent value also fulfills the specification value of < 1 ppm. It can be concluded from this study that the graphite purified by acid leaching with HF can be used as fuel matrix candidate but is qualified as low quality. Futher research is required to produce high quality nuclear graphite, particularly research in the minimization of the impurity by evaporation at temperatures over 950 oC to by far lower the ash content.Keywords:  Indonesian natural graphite, purification, nuclear fuel matrix, acid leaching, chemical characterization.

Metode tidak langsung pengujian klorida dilakukan dengan mereaksikan klorida dengan perak berlebih, kemudian kadar perak sisa yang tidak bereaksi dihitung. Penelitian ini bertujuan untuk mengetahui kelayakan suatu metode melalui beberapa parameter, seperti linieritas, akurasi dan presisi, limit kuantitasi, dan limit deteksi instrumen pada sampel tanpa matriks (A), sampel UO2 dengan penambahan larutan standar Cl setelah ekstraksi (B) dan sampel UO2 dengan penambahan larutan standar Cl sebelum ekstraksi (C).Diperoleh nilai regresi linier pada sampel A sebesar 0,997, pada sampel B sebesar 0,996, dan pada sampel C sebesar 0,995. Nilai recovery yang didapat pada sampel A sebesar 102,804 %, pada sampel B sebesar 98,924 %, dan pada sampel C sebesar 98,096 %.Nilai simpangan baku relatif yang didapatkan pada sampel A sebesar 1,4 %, pada sampel C sebesar 0,2 %, dan pada sampel B sebesar 0,5 %. Nilai limit deteksi pada sampel dengan matriks yang didapat dengan metode ini, yaitu 0,0958 µg/g dan 0,1024 µg/g, sedangkan nilai limit kuantitasi pada sampel dengan matriks yaitu 0,3195 µg/g dan 0,3415 µg/g. Berdasarkan hasil penelitian, dapat dinyatakan bahwa metode tervalidasi dan layak diterapkan di Laboratorium Kendali Kualitas -Instalasi Elemen Bakar Eksperimental.