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Articles

Effect of Heating Treatment on Synthetic Ceric Oxide as Inorganic Resin for Immobilization of Cadmium-(II) Soenarjo, S; Wijaya, C; Elzan, R; Sriyono, Sriyono
Atom Indonesia Vol 31, No 1 (2005): January 2005
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (329.176 KB) | DOI: 10.17146/aij.2005.124

Abstract

The immobilization of cadmium-(II) following nuclear reaction of 114Cd (n,γ) 115Cd → 115mIn or 112Cd (p,2n) 111In is absolutely needed concerning to the quality of resulting radioisotope products and the efficiency of enriched target utilization. This presented study is based on hypothesis that heating treatment on synthetic ceric oxide resin will increase the binding capacity of Cd(II) over the resin. The aim of the presented study is to gain more experimental data supporting utilization of synthetic ceric oxide resin as separating agent in production of indium radioisotopes using enriched cadmium targets. Experiments in cold system using natural cadmium, instead of high-enriched cadmium, have been carried out, wherein a method of UV-spectrophotometry was performed for quantitative determination of Cd(II). It was found that the synthesized ceric oxide dried at 90 - 100°C was in form of hydrate compound formulated as CeO2.q H2O where q = (0.8868 ± 0.0026). The value of q descended to 0.1706 and to 0.0400 as influenced by heating treatment up to 400°C and 800°C respectively along with a change on the crystallinity of the ceric oxide from semi crystalline to purely crystalline. The binding capacity of Cd(II) on ceric oxide dried at 90 – 100°C was found to be (4.71 ± 0.08) × 10-2 mg Cd(II)/mg resin and significantly increased to (11.71 ± 0.24) × 10-2 and to (14.70 ± 0.17) × 10-2 mg Cd(II)/mg resin due to heating treatment up to 400°C and 800°C respectively. It can be concluded that the synthetic ceric oxide resin enable to be exploited for immobilization of Cd(II).
Separation of Radiocopper 64/67Cu from the Matrix of Neutron-Irradiated Natural Zinc Applicable for 64Cu Production Soenarjo, S.; Sriyono, Sriyono; Rahman, W.Y.; Sarmini, E.; Hambali, Hambali; Triyanto, Triyanto
Atom Indonesia Vol 38, No 1 (2012): April 2012
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (237.644 KB) | DOI: 10.17146/aij.2012.136

Abstract

Radioisotope 64Cu is a promising radiometallic-isotope for molecular-targeted-radiopharmaceuticals. Having a half-life of 12.70 hours and emitting β+-radiation (Eβ+ = 0.6531 MeV) as well as β-ray (Eβ- = 0.5787 MeV), it is widely used in the form of biomedical-substrate-radiopharmaceutical for positron emission tomography (PET) diagnosis and simultaneously for targeted radiotherapy of cancer. The potential needs on the availability of 64Cu-labeled pharmaceuticals for domestic nuclear medicine hospitals lead to a necessity for the local production of carrier-free 64Cu using BATAN’s G.A. Siwabessy reactor because of the technical and economical constraints in the production using BATAN’s cyclotron. The presented work is accordingly to study whether the radioisotope 64Cu can be produced and separated from the matrix of post-neutron-irradiated-natural zinc. This study is expected can be further improved and implemented in production technology of carrier-free 64Cu based on 64Zn (n,p) 64Cu nuclear reaction exploiting the fast neutron fraction among the major thermal fraction due to unavailability of fast-neutron-irradiation facility in the BATAN’s G.A. Siwabessy reactor. The solution of post-neutron-irradiated-natural zinc in 1M acetic acid was loaded into Chelex-100 cation exchanger resin column to pass out the Zn/Zn* fraction whereas the Cu* fraction which remained in the column was then eluted out from the column by using 1.5 M HCl and loaded into the second column containing Dowex-1X8 anion exchanger resin. The second column was then eluted with 0.5 M HCl. The collected eluate was expected to be zinc-free Cu* fraction. It was observed from the half-life and the γ-spectrometric analysis that radioactive copper-64Cu containing 67Cu was produced by neutron activation on the natural Zn-foil target and can be separated from the target matrix by the presented two-steps-column-chromatographic separation technique. The radioactivity measurement showed that wrapping the Zn target with cadmium foil increased the activity of radioactive copper and, thus, the Cu*/Zn*-ratio.Received: 28 June 2011; Revised: 21 February 2012; Accepted: 24 February 2012
UJI PRODUKSI Mo-99 HASIL FISI DENGAN BAHAN SASARAN FOIL LEU BUATAN P2TBDU-BATAN Lubis, Hotman; Muthalib, Abdul; Gunawan, Adang H.; Sriyono, Sriyono; Sucipto, Edi; Hambali, Hambali
Jurnal Radioisotop dan Radiofarmaka Vol 8 (2005): JURNAL PRR 2005
Publisher : Jurnal Radioisotop dan Radiofarmaka

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Abstract

UJI PRODUKSI Mo-99 HASIL FISI DENGAN BAHAN SASARAN FOIL LEU BUATAN P2TBDU-BATAN. Selama ini telah dilaksanakan beberapa kali produksi Mo-99 dengan menggunakan bahan sasaran foil LEU buatan Argonne National Laboratory (ANL). Dalam produksi Mo-99 dengan proses Cintichem yang dimodifikasibahan sasaran foil LEU sangat menentukan. Telah dilakukan uji produksi Mo-99 hasil fisi dengan bahan sasaran foil LEU (LEU, < 20% U-235) buatan P2TBDU-BATAN dengan proses Cintichem yang dimodifikasi, meliputi pelarutan foil LEU menggunakan HNO3 9,5N, penarikan gas iodium, proses pemisahan dengan pengendapan α-Benzoin Oxime dan pemurnian Mo-99 melalui kolom kromatografi. Foil LEU larut dengan sempurna selama 30 menit dan penarikan gas iodium dilakukan dengan pendinginan nitrogen cair. Setelah melalui tahap pemisahan (pengendapan) dan pemurnian kolom I dan kolom II radionuklida pengotor masih besar dan aktivitas pengotor pemancar α melebihi persyaratan standard internasional yang ditetapkan yaitu sebesar 7.716E-7 µCi/mCi Mo-99. Kata kunci: produksi Mo-99 HF, Sasaran Foil LEU P2TBDU PRODUCTION TEST OF Mo-99 FISSION PRODUCT USING LEU TARGET FOIL MADE IN P2TBDU – BATAN. Production of Mo-99 fission product using LEU target foil of Argonne National Laboratory (ANL) has been performed several times recently in BATAN. In the production of Mo-99 using modified Cinthichem method, the LEU target foil was very critical. This paper reported production test on Mo-99 fission product using LEU target foil ( LEU < 20% U-235) made by P2TBDU – BATAN using modified Cintichem method. The process included dissolving of LEU foil with 9.5 N HNO3, suctioning of iodine gas, separation process using precipitation with α–benzoin oxime, and purification by column chromatography. The LEU foil was completely dissolved after 30 minutes and gas suction was performed by cooling with liquid nitrogen. After separation and two purification steps, the radionuclide impurities were remained high and activity of αimpurities exceeded international standard requirements, i.e. 7.716E-7 µCi/mCi Mo-99. Key words: Production of Mo-99 FP, Target foil LEU P2TBDU
UPAYA PERLINDUNGAN TERHADAP AIR TANAH DARI KERUSAKAN SEBAGAI DAMPAK PENGEMBANGAN PEMUKIMAN (Studi Kasus di Kabupaten Sukoharjo Sriyono, Sriyono
Teknik Sipil dan Arsitektur Vol 2, No 4 (2002): jurnal teknik sipil dan arsitektur
Publisher : Teknik Sipil dan Arsitektur

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Abstract

Penelitian ini dilakukan dengan tujuan untuk mengetahui efektifitas peraturan perlindungan air tahan terhadap dampak pengembangan permukiman masalah apa yang terjadi dan pola perlindungan yang telah ada adapat dikembangkan. Tujuan penelitian ini untuk mengetahui apakah upaya perlindungan sember air bawah tanah terhadap dampak pengembangan permukiman di Kabupaten Sukoharjo merupakan masalah-masalah apa yang terjadi dalam pelaksanaan pembangunan pemukiman, upaya-upaya apakah yang dapat dilakukan untuk mengatasi masalah-masalah tersebut, dalam rangka mengembangkan pola perlindungan hukum yang lebih baik. Metode penelitian yang digunakan adalah deskriptif dengan pendekatan kualitatif abstrak indikatif. Pendekatan yang dilakukan adalah yuridis empirisatau yuridis sosiologis. Data yang digunakan meliputi data primer dan data sekunder. Penelitian dilakukan di Kabupaten Sukoharjo. Areal permukiman yang diteliti dipilih secara “purposive”. Responden penelitian dipilih secara “non probability”. Responden diambil dari pengembang, masyarakat penghuni, aparat yang terkait. Data priper diperoleh dengan mempergunakan “content identification”. Analisis data secara kualitatif yaitu dengan model analisis interaltif. Hasil penelitian yang dilakukan menghasilkan temuan bahwa pada pola perlindungan sumber air bawah tanah dari kerusakan sebagai dampak dari pengembangan permukiman di Kabupaten Sukoharjo sudah dapat memberi hasil yang efektif. Dair data penelitian ini karena pengembangan permukiman dilakukan tidak pada daerah tangkapan hujan, ruang terbuka yang tersedia. Luas lahan yang dikembangkan masih memenuhi persyaratan yaitu lebih dari 40% penggunaan sumber air tanah oleh penghuni permukiman masih sangat terbatas. Masalah-maslah yang ditemukan antara lain belum lengkap peraturan perundangan yang diperlukan, belum ada kelembagaan yang secara khusus menangani perijinan dan pengawasan, fasilitas jalan permukiman berupa aspal sehingga tidak memberi efek resapan air, koefisien dasar bangunan yang melebihi standart karena belum adanya fasilitas sumur resapan masih kurangnya pemahaman tentang pengaturan arti penting sumber air bawah tanah. Pola perlindungan yang perlu dikembangkan berupa penyusunan Peraturan Daerah yang mencakup perijinan tentang pembangunan permukiman baru dan perijinan penggunaan/eksploitasi air tanah. Disamping itu, diperlukan pembentukan suatu kelembagaan yang terintregasi yang melibatkan instansi teknis terkait lainnya di bidang perijinan dan pengawasan terhadap eksploitasi air tanah. Dari hasil pembahasan didapat saran berupa perlu dilakukan penelitian labih lanjut pada berbagai daerah lain untuk digunakan sebagai perbandingan dalam rangka merumuskan pola perlindungan hukum yang lebih tepat terhadap air tanah dari kerusakan akibat pengembangan permukiman.
STUDI SISTEM KESELAMATAN TEKNIS REAKTOR SMART Alimah, Siti; Dewita, Erlan; Sriyono, Sriyono
Jurnal Forum Nuklir JFN Vol 8 No 2 November 2014
Publisher : BATAN

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Abstract

STUDI SISTEM KESELAMATAN TEKNIS REAKTOR SMART. Indonesia merupakan negara kepulauan yang terdiri dari banyak pulau besar dan kecil. Kebutuhan energi terutama pada pulau-pulau kecil sampai saat ini belum dapat terpenuhi. Untuk memenuhi kebutuhan energi tersebut, penggunaan energi nuklir dapat menjadi salah satu solusi. Reaktor SMART merupakan salah satu reaktor nuklir berdaya kecil sekitar 90 MWe, dan 10% energinya dapat digunakan untuk produksi air bersih dengan proses desalinasi. Reaktor SMART memiliki dua macam fitur keselamatan yaitu sistem keselamatan melekat (inherent) dan system teknis pasif (passive system). Makalah ini membahas kajian sistem keselamatan teknis reaktor SMART. Tujuan studi adalah memperoleh pemahaman aspek keselamatan teknis reaktor SMART, sebagai masukan pengambil keputusan untuk penimbangan pemilihan teknologi reaktor. Studi dilakukan melalui kajian pustaka. Sistem keselamatan teknis pasif yang diimplementasikan pada SMART adalah sistem shutdown (pemadaman), sistem pengambilan panas sisa pasif, sistem pendinginan teras darurat pasif, sistem proteksi sungkup terhadap tekanan lebih. Disamping itu, sistem proteksi reaktor terhadap tekanan lebih dan beberapa sistem yang memitigasi kecelakaan, juga di tambahkan. Fungsi sistem keselamatan teknis adalah menjaga kestabilan pendinginan reaktor agar tidak terjadi pemanasan berlebih pada sistem pembangkit serta mencegah terlepasnya produk radioaktif ke lingkungan dan melakukan pemadaman reaktor setiap saat diperlukan. Hasil studi menunjukkan bahwa pengamanan sistem keselamatan teknis pasif mampu mengurangi penggunaan pompa, katup dan perpipaan sehingga meningkatkan kemudahan konstruksi, operasi dan perawatan sistem, serta mengurangi tindakan operator. Apabila dibandingkan, reaktor SMART hanya memerlukan sekitar 180 katup, jauh lebih sedikit dibandingkan dengan reaktor PWR konvensional 1000 MW, yang memerlukan 1100 katup.Kata Kunci: keselamatan teknis, reaktor, SMART, PWR, sistem pasif
SIMULATIONS ON NICKEL TARGET PREPARATION AND SEPARATION OF Ni(II)- Soenarjo, Sunarhadijoso; Rahman, Wira; Sriyono, Sriyono; Triyanto, Triyanto
Jurnal Iptek Nuklir Ganendra Vol 14, No 1 (2011)
Publisher : BATAN

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Abstract

SIMULATIONS ON NICKEL TARGET PREPARATION AND SEPARATION.OF Ni(II)-Cu(II) MATRIX FORPRODUCTION OF RADIOISOTOPE64Cu64Ni (p,n) 64  and retained on the column while the nickel was kept in the form of Ni2+  2+  2+ and CuCl while the nickel was totally in the form of Ni2+  while the nickel was found as both Ni2+ and NiCl   while the nickel was mostly in the form of Ni2+. The retained CuCl was then changed back into Cu2+     Keywords 64 Cu, Anion exchange chromatography.: Nickel target preparation, Radioisotope Cu-64, Separation of Ni(II)-Cu(II) matrix, Nuclear reaction of 64Ni(p,n) cation form andeluted out the column by using HCl 0.05 M. The 42– 4 2–.The best condition of separation was in HCl 8 M in which the radioactive copper was mostly in the form of CuCl 42– 42– . In the condition ofHCl 9 M, the radioactive copper was mostly in the form of CuCl 42– cation. It was found that the electroplating result from the acidic solution was more satisfied than that from the basic solution. By conditioning the matrix solution at HCl 6 M, the radioactivecopper was found in the forms of Cucation and eluted off from the column. The retained radioactive copper was then eluted out the column in the condition of dilute HCl changingback the copper anion complex into Cu42– Cu. The nickel target preparation was performed by means of electroplating method using acidic solution of nickel chloride - boric acid mixture and basic solution of nickel sulphate – nickel chloridemixture on a silver- surfaced-target holder. The simulated solution of Ni(II) – Cu(II) matrix was considered as thesolution of post-proton-irradiated nickel target containing both irradiated nickel and radioactive copper, but in thepresented work the proton irradiation of nickel target was omitted, while the radioactive copper was originallyobtained from neutron irradiation of CuO target. The separation of radioactive copper from the nickel target matrixwas based on anion exchange column chromatography in which the radiocopper was conditioned to form anioncomplex CuClg-spectrometric analysis showed a single strong peak at 511 keVwhich is in accord to g-annihilation peak coming from positron decay of Cu-64, and a very weak peak at 1346 keVwhich is in accord to g-ray of Cu-64.. The simulations on Nickel target preparation and separation of Ni(II)- Cu(II) matrix has been carried out as a preliminary study for production of medical radioisotope Cu-64 based onnuclear reaction of
TERJEMAHAN CONJUNCTIVE RELATION (CR) DALAM NOVEL MIXED BLESSINGS DAN NOVEL BERKAH PENUH COBAAN Sriyono, Sriyono
LiNGUA: Jurnal Ilmu Bahasa dan Sastra Vol 6, No 1 (2011): LiNGUA
Publisher : Faculty of Humanities, Universitas Islam Negeri Maulana Malik Ibrahim Malang

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.18860/ling.v6i1.1297

Abstract

This paper discusses the form and meaning of conjunctive relation and how conjunctive relation is translated from source language into target language. The different system amongst languages  in forming words, sentences or paragraph might  represent  peculiar form and meaning. As a part of element in determining logical meaning, conjunctive relation can be in the  form of conjunction, verb, noun, preposition and implicit. Those forms signal how unity of a text is constructed. In translation, the use of conjunctive relation forms frequently make problem for translators since it is closely related to logical meaning in a text.  In translating text, different meaning between two languages should be occasionally translated into different form and meaning of the two languages. To understand a text comprehensively, a reader must know the unity of a text. One of the aspects to determine unity of a text in translation is conjunctive relation. The unity of a text can be covered with the conjunctive relation which signal logical relation among clauses, sentences and paragraph, so that in translation cohesiveness of a text is interpreted well both in source text and target text.Keywords: Terjemahan, Conjuctive, Relation, Makna, Logis
PRODUKSI TEMBAGA-64 MENGGUNAKAN SASARAN TEMBAGA FTALOSIANIN Awaludin, Rohadi; Abidin, Abidin; Sriyono, Sriyono; Herlina, Herlina
Jurnal Radioisotop dan Radiofarmaka Vol 9 (2006): jurnal PRR 2006
Publisher : Jurnal Radioisotop dan Radiofarmaka

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Abstract

PRODUKSI TEMBAGA-64 MENGGUNAKAN SASARAN TEMBAGA FTALOSIANIN. Radioisotop tembaga-64 (64Cu) merupakan pemancar positron yang memiliki beberapa kegunaan. Radioisotop ini dapat diproduksi dari 63 Cu melalui aktivasi neutron. Untuk mendapatkan radioisotop dengan radioaktivitas jenis yang tinggi, radioisotop ini dapat diproduksi memanfaatkan reaksi Szilard Chalmer, yaitu memanfaatkan lepasnya 64 Cu hasil iradiasi dari matrik sasaran. Tujuan dari penelitian ini adalah mendapatkan karakteristik 64Cu yang dapat diproduksi menggunakan reaktor G.A. Siwabessy dari sasaran tembaga ftalosianin. Tembaga ftalosianin sebanyak 200 mg diiradiasi di posisi pneumatic rabbit system selama 30 menit. Hasil iradiasi diukur menggunakan gamma ionization chamber untuk mendapatkan radioaktivitas yang dihasilkan. Kemurnian radionuklida diukur menggunakan spektrometer gamma. Dari tiga kali iradiasi diperoleh 64 Cu dengan radioaktivitas sebesar 5,29; 5,70 dan 5,65 mCi. Dari pengukuran menggunakan spektrometer gamma diketahui bahwa tidak ada radionuklida lain yang terdeteksi. Dari pemisahan menggunakan metode emulsi masih diperoleh yield yang rendah sebesar 2,59; 3,18 dan 5,33%. Kata kunci: tembaga-64, produksi radioisotop, tembaga ftalosianin PRODUCTION OF COPPER-64 USING COPPER PHTHALOCYANINE TARGET. Copper-64 is a positron emmiter radioisotope with a wide range of applications. The radioisotope can be produced by neutron activation method from 63 Cu. For obtaining high specific radioactivity, Szilard Chalmer method can be applicated, using the recoiling of 64 Cu from the target matrix. The objective of this study is obtaining the characteristics of 64 Cu that is produced using G.A. Siwabessy reactor with copper phthalocyanine target. Copper phthalocyanine 200 mg was irradiated at pneumatic rabbit sytem of GA Siwabessy reactor for 30 minutes. The radioactivity of Cu was measured by gamma ionization chamber. The radionuclide purity was determined by gamma spectrometer. From 3 times of irradiation of 200 mg of copper phthalocyanine, the Cu as high as 5.29, 5,70 and 5,65 mCi was obtained. The results of gamma spectrometer measurement showed that any other radioisotopes were not detected. Low yield (2.59; 3.18 and 5.33%) was obtained by separation using emulsion method. Key words: Copper-64, radioisotope production, copper phthalocyanine.
PEMISAHAN FRAKSI OSMIUM DAN IRIDIUM DALAM MATRIKS OSMIUM ALAM PASCA IRADIASI DENGAN TEKNIK EKSTRAKSI PELARUT Kadarisman, Kadarisman; Lubis, Hotman; Sriyono, Sriyono; Abidin, Abidin
Jurnal Radioisotop dan Radiofarmaka Vol 10 (2007): JURNAL PRR 2007
Publisher : Jurnal Radioisotop dan Radiofarmaka

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Abstract

PEMISAHAN FRAKSI OSMIUM DAN IRIDIUM DALAM MATRIKS OSMIUM ALAM PASCA IRADIASI DENGAN TEKNIK EKSTRAKSI PELARUT. Generator Osmium – Iridium ada dua macam, yaitu generator radioisotop 191Os – 191mIr dan 194Os – 194Ir. Radioisotop 191mIr dan 194Ir digunakan di bidang kesehatan, terutama untuk diagnosis fungsi ginjal dengan metoda Angiografi. Dalam penelitian ini dilakukan pemisahan 191Os dari 192Ir melalui tahapan tahapan penelitian; penyiapan target Osmium alam, iradiasi target, perlakuan target teriradiasi, yang meliputi pengangkutan target teriradiasi ke fasilitas hot cell, pembukaan tabung dan pelarutan, serta proses pemisahan Osmium teriradiasi dengan ekstraksi pelarut menggunakan CCl4. Analisis radionuklida 191Os dan 192Ir menggunakan spektrometer gama. Dari hasil percobaan ini diperoleh radionuklida 191Os dan 192Ir dalam Osmium alam teriradiasi masing-masing sebesar 87,88 µCi dan 20,01 µCi saat pemisahan. Radionuklida 191Os dapat dipisahkan dari pengotor radionuklida 192Ir dengan radioaktivitas total 14,83 µCi dengan efisiensi pemisahan sebesar 16,88% pada akhir pemisahan. Hal ini menunjukkan kemungkinan dapat dipreparasi radionuklida 191Os atau 194Os untuk bahan generator 191Os/191mIr dan 194Os/194Ir. Kata Kunci : Osmium-191, Iridium-192, Ekstraksi, Generator 191Os/191mIr atau 194Os/194Ir THE SEPARATION OF FRACTION OF OSMIUM AND IRIDIUM IN OSMIUM MATRIX IRRADIATED WITH THE EXTRACTION LIQUID TECHNIQUE. Generator Osmium - Iridium there is 2 kinds of, that is radioisotope generator 191Os/191mIr dan 194Os/194Ir. Radioisotope 191mIr and 194Ir used in health area, especially to be diagnosed to a kidney function with the Angiography method. In this development conducted separation 191Os from 192Ir through research step; experienced Osmium target preparation, target irradiation, treatment of target irradiated, covering the transportation of target irradiated to facility of hot cell, opening save and dissolution, and also separation process of Osmium irradiated by solvent extraction use the CCL4. Analysis the radionuclide of 191Os and 192Ir use the gamma spectrometer. From this attempt result is obtained 191Os and 192Ir in Osmium irradiated each of 87,88 µCi and 20,01 µCi of dissolution moment. Radionuclide 191Os is detachable from 192Ir radionuclide impurities with the total radioactivity 14,83 µCi with the dissolution efficiency of equal to 16,88% by the end of dissolution. This matter show the possibility earn the preparation radionuclide 191Os atau 194Os for the substance of generator 191Os/191mIr or 194Os/194Ir. Keywords : Osmium-191, Iridium-192, Extraction, 191Os/191mIr or 194Os/194Ir Generator.
PENGEMBANGAN PROSES PRODUKSI MOLIBDENUM-99 HASIL FISI DENGAN MENGGUNAKAN TARGET FOIL LOGAM Uranium PENGKAYAAN RENDAH Mutalib, Abdul; Vandegrift, G. F.; Conner, C.; Gunawan, Adang Hardi; Lubis, Hotman; Sukmana, Ateng; Purwadi, Bambang; Wisnukaton, Khadarisman; Jatmiko, Diki Tri; Sriyono, Sriyono
Jurnal Radioisotop dan Radiofarmaka Vol 3, No 1 (2000): JURNAL PRR 2000
Publisher : Jurnal Radioisotop dan Radiofarmaka

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Abstract

PENGEMBANGAN PROSES PRODUKSI MOLIBDENUM-99 HASIL FISI DENGAN MENGGUNAKAN TARGET FOIL LOGAM URANIUM PENGKAYAAN RENDAH. Badan Tenaga Nuklir Nasional dan Argonne National Laboratory dewasa ini sedang melaksanakan kerja sama penelitian dan pengembangan produksi molibdenum-99 dengan menggunakan foil logam uranium pengkayaan rendah. Pembahasan dalam makalah ini lebih difokuskan terhadap hasil kerja sama pengembangan dan penelitian tersebut yang telah dilaksanakan di Pusat Pengembangan Radioisotop dan Radiofarmaka. Dalam makalah dijelaskan (1) keberhasilan pemisahan dan pemurnian 99Mo dari target foil logam uranium pengkayaan rendah yang telah diiradiasi di reaktor RSG-GA Siwabesy, dan (2) keberhasilan memodifikasi proses Cintichem. Hasil pengembangan pendahuluan metoda kuantitatif elektrodeposisi cemaran uranium dan plutonium di dalam 99Mo juga akan dijelaskan. DEVELOPMENT OF PRODUCTION PROCESSES OF FISSION PRODUCT MOLYBDENUM-99 USING LEU METAL FOIL TARGETS. A collaboration is underway between Indonesian National Nuclear Energy Agency and Argonne National Laboratory to carry out R&D on the production of molybdenum-99 using LEU (Low Enriched Uranium)-metal foil targets. A review in this paper is focused mainly on the results of laboratory experiments conducted at the Center for Development of Radioisotopes and Radiopharmaceuticals, Serpong. It describes succeses in (1) performing separation and purification of 99Mo in the irradiated LEU-metal foil targets, and (2) modifying Cintichem procedure. A method for quantitatively electrodepositing uranium and plutonium contaminants in the 99Mo is also described.
Co-Authors Abdul Hafid Abdul Hafidz Abdul Mutalib Abdul Muthalib Abidin Abidin Adang H. Gunawan Adang Hardi Gunawan Adi Santoso Afandi, Alfid Tri Agung S, Daya Agus, Mohamad Agustin, Cyntia ah. Yusuf Ali Ahmadi Alimudin, Imam A. amita asih ardiyanti, amita asih Ananto Aji, Ananto Anas, Ma’ruf M Andriana Andriana, Andriana Anung Pujianto Apik Budi Santoso Aprianto, Ary Arifal Arifal, Arifal Astuti, Dian Eko Puji Ateng Sukmana Bahar, Febrianto Bambang Purwadi Budi, Andi Setyo Budiyanto Budiyanto Butar-butar, Sofia Loren C Wijaya C. Conner Dadang Haffid Daniel Santoso Deni Yasmara, Deni Desi Inayati, Desi Dewi Liesnoor Setyowati Diki Tri Jatmiko Diyah E. Lestari, Diyah E. Diyah Erlina Lestari Dwi Amri Wibowo, Dwi Amri Dwi Irmawati, Dwi E. Lestari, E. E. Sarmini Edi Sucipto Elina Rifda Rakhmawati, Elina Elisabeth Ratnawati Endang Sarmini Enny Lestari Erlan Dewita Erni Puji Astuti Erni Suharini Ester Gita Kartika, Ester Gita Eva, Banowati Fajarianto, Adi Cahyo Febrianto Febrianto, Febrianto G. F. Vandegrift Geni Rina Sunaryo Gunawan, A. H. H. Setiawan Hadirahman, Hadirahman Hakim Zulkarnain, Hakim Hambali Hambali HARIYANTO HARIYANTO Harmayetty Harmayetty, Harmayetty Hendra Prasetya Heri Tjahjono Herlan Setiawan Herlina Herlina Hilda, Atiqah M. Hotman Lubis Ibon Suparman Ignatius Djoko Irianto, Ignatius Djoko Ilham Ilham Imam Saputra Indra Kustiawan, Indra Indra Saptiama Iqlima Dwi Kurnia, Iqlima Dwi Irnawati, Isnaini Rahmatia Is One Nugroho, Is One Istiqomah, Rizkiani Maghfirotun Itjeu Karliana, Itjeu Joni Haryanto Kadarisman Kadarisman Kadarisman Wisnukaton Kamayani, Mia Khadarisman Wisnukaton Kurniawan, Eko Setyadi kurniyawan, enggal hadi Kusmiati Kusmiati Kusnanto Kusnanto Laili, Nadia Rohmatul M ROMLI, M Maman Rakhman, Maman Marlina Marlina Marlina, Marlina Meitasari, Rizki MN, Kholid Rosyidi Moch. Arifien, Moch. Moch. Wahyu Riyanto, Moch. Wahyu Moh Ayodhia Soebadi Muhammad Khafid A. Mutaqin, Muhammad Khafid A. Mumu Komaro, Mumu Munir, Miftakul Nila Kurniasih Ninuk Dian Kurniawati, Ninuk Dian Nugraha, Ahmad Hutama Adhi Nur, Rokhayati Nursalam Nursalam Nuryovi, Nuryovi Oktiana, Cichi Ono Wiharna, Ono Otty Damayanti Utami, Otty Damayanti P, Anung Pahlevi, Rifka Piping Supriatna, Piping Piping Supriyatna, Piping Pohan, Rezka B. Prapanca, Detak Pujiono, Horen Purwoko, Riawan Yudi Putri Nur Fitria, Putri Nur Qona’ah, Arina R Elzan R Sugiyanto Rahayu Kusumastuti Rochmah, Aini Nur Khoirurrizqi Rohadi Awaluddin Rohadi Awaludin Roziq Himawan Rukman Rukman S Soenarjo S. Soenarjo Sagino Sagino Salma, Muvidayanti Saptono Putro Sarwono, D. Agung Sasmita, Iwan Widia Sati, Esti Laras Satyanta Parman Setiyawati, Sri Siti Alimah Sofia Butarbutar, Sofia Sofia Loren Butarbutar, Sofia Loren Sudono Salim Raharjo, Sudono Salim Suhartono Taat Putra Sukrisno, Adi Sulistiyo, Bayu D. Sumaryo Sumaryo Sumijanto Sumijanto, Sumijanto Sunarhadijoso Soenarjo Sunarko Setyawan, Sunarko Susanty Susanty, Susanty Syafrul Syafrul Tarmono Djojodimedjo Tatang Permana, Tatang Tintin Sukartini, Tintin Tjaturahono Budi Sanjoto Togar Marsangap Ritonga Topan Setiadipura, Topan Triani Widyaningrum Triyanto Triyanto Umi Pratiwi, Umi W.Y. Rahman Wahid Munawar Wahyu Setyaningsih Wahyuni, Erna Dwi Wahyuningsih, Reny Widodo J Pudjirahardjo Widyastuti Widyastuti Wira Rahman Wira Y. Rahman Wowo S. Kuswana, Wowo S. Yayan Tahyan Yulis Setiya Dewi, Yulis Setiya Yustinus Purwamargapratala Zamzany, Faizal Ridwan