Ganendra Majalah IPTEK Nuklir最新文献

{"title":"PENGARUH DOSIS IMPLANTASI ION NITROGEN PADA SIFAT KAPASITASI POLIMER PVDF DAN PVDF-HFP","authors":"Riza Nor Hudayawan, D. Darsono, Damar Yoga Kusuma","doi":"10.17146/GND.2018.21.2.4486","DOIUrl":"https://doi.org/10.17146/GND.2018.21.2.4486","url":null,"abstract":"Material berdensitas energi elektrik tinggi sebagai bahan dielektrik kapasitor sangat diperlukan dalam industri bidang elektronika. Tujuan penelitian ini ialah mengkarakterisasi dan menganalisis polimer PVDF( Poly vinylidene fluorde) dan PVDF-HFP (Poly vinylidene fluoride-co-hexafluoropropene)  sebelum dan sesudah diimplan ion nitrogen. Metode penelitian yang dilakukan ialah menyiapkan sampel lapisan tipis Polimer PVDFdan PVDF-HFP kemudian diimplan menggunakan ion nitrogen pada dosis 4,69 x 1016 ion/cm2 hingga 1,41 x 1018 ion/cm2 pada energi 10 keV. Selanjutnya nilai kapasitansi, faktor disipasi dan kekuatan dielektrik sampel dikarakterisasi menggunakan LCR meter GW-Instek 800. Morfologi dan ikatan struktur dari sampel dikarakterisasi menggunakan SEM dan FTIR. Hasil percobaan menunjukkan bahwa terjadi peningkatan nilai kapasitansi sebesar 4,3 kali pada polimer PVDF dan 1,4 kali pada polimer PVDF-HPF. Peningkatan nilai kapasitansi disebabkan bertambahnya ikatan rangkap C=C pada PVDF dan PVDF-HFP yang diimplan ion nitrogen. Hal tersebut dibuktikan dari hasil karakterisasi FTIR dan SEM. Namun demikian nilai kekuatan dielektrik mengalami penurunan akibat semakin konduktifnya polimer PVDF dan PVDF-HPF. Untuk sampel PVDF ada kapasitansi optimum dicapai pada dosis 9,38 x 1017 ion/cm2 sedangkan untuk sampel PVDF-HFP diatas dosis tersebut memperlihatkan gejala saturasi. Nilai kapasitansi optimal diperoleh berturut-turut sebesar 0,089483 nF, faktor disipasi 0,129613 % pada polimer PVDF dan 0,134889 nF, faktor disipasi 0,09784 % untuk polimer PVDF-HFP.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"29 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-11-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"77818754","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"KARAKTERISASI LIMBAH DARI PRODUKSI RADIOISOTOP MOLIBDENUM-99","authors":"A. Aisyah, P. A. Artiani, Yuliman Purwanto","doi":"10.17146/gnd.2018.21.2.4148","DOIUrl":"https://doi.org/10.17146/gnd.2018.21.2.4148","url":null,"abstract":"KARAKTERISASI LIMBAH DARI PRODUKSI RADIOISOTOP MOLIBDENUM-99.  Radioisotop 99Mo diproduksi terutama sebagai radioisotop induk untuk memperoleh radioisotop tecnisium-99m (99mTc). Radioisotop 99mTc dipakai dalam kedokteran nuklir antara lain  untuk diagnosis pada kelainan tulang, otak, thyroid, paru-paru, hati dan ginjal. Di Indonesia 99Mo diproduksi oleh PT. Industri Nuklir Indonesia (INUKI) dari target uranium yang dilekatkan kedalam dinding kapsul baja tahan karat untuk kemudian diiradiasi di Reaktor GA Siwabessy. Pengambilan 99Mo dalam target dilakukan dengan proses CINTICHEM. Pada proses CINTICHEM akan ditimbulkan  beberapa jenis limbah yang salah satunya adalah Radioactive Fission Waste (RFW). Limbah ini memiliki paparan radiasi yang besar yang mengakibatkan karakterisasi limbah secara laboratorium sulit dilakukan. Pengelolaan limbah yang tepat memerlukan karakteristik limbah yang tepat pula. Oleh karena itu dalam penelitian ini dilakukan karakterisasi limbah RFW menggunakan program komputer ORIGEN 2.1 dengan data parameter input adalah data dari salah satu batch produksi 99Mo di PT INUKI yang berupa data target uranium diperkaya tinggi 92,7% yang dilekatkan pada kapsul baja tahan karat AISI 304L, iradiasi dilakukan pada posisi Centre Irradiation Position (CIP) dalam Reaktor Serbaguna GA Siwabessy dengan fluks netron termal: 1,12x1014 n/cm2detik dan iradiasi target dilakukan selama 96 jam. Seleksi radionuklida yang relevan terhadap metode pengelolaan limbah dilakukan berdasarkan pada waktu paro, tingkat kliren dan radiotoksisitas. Hasil penelitian menunjukkan bahwa sampai dengan waktu peluruhan 50 tahun, total konsentrasi aktivitas limbah 3,01x109 Bq/g dengan kandungan radionuklida produk aktivasi, aktinida dan anak luruhnya serta produk fisi. Selain itu limbah ini juga mengandung 235U yang masih cukup besar serta radionuklida umur paro panjang dengan tingkat toksisitas yang sangat tinggi. Berdasarkan pada Peraturan Pemerintah No.61 Tahun 2013 limbah ini diklasifikasikan sebagai limbah radioaktif  tingkat sedang dan memerlukan pengelolaan dengan tingkat keselamatan yang tinggi.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"42 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-08-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80435536","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"PENGUKURAN SPEKTRUM NEUTRON PADA TABUNG BERKAS NEUTRON RADIOGRAFI REAKTOR G.A. SIWABESSY DENGAN SINGLE SPHERE SPECTROMETER","authors":"Rasito Tursinah, Bunawas Bunawas, U. Tarmulah, S. Zanuar, D. Andrega","doi":"10.17146/gnd.2018.21.2.4316","DOIUrl":"https://doi.org/10.17146/gnd.2018.21.2.4316","url":null,"abstract":"Telah dilakukan pengukuran spektrum neutron pada tabung berkas neutron fasilitas radiografi neutron reaktor G.A Siwabessy. Pengukuran dilakukan untuk mengkonfirmasi adanya faktor penyebab menurunnya kualitas ketajaman citra hasil dari radiografi. Pengukuran spektrum neutron dilakukan menggunakan single sphere spectrometer (SSS) dengan tujuh detektor keping emas. Tampilan spektrum neutron dari konversi aktivitas detektor SSS dilakukan menggunakan software UMG 3.3, adapun fungsi respon detektor SSS dihitung menggunakan software MCNPX. Berdasarkan hasil pengukuran diperoleh spektum neutron didominasi termal dengan fluks termal 6,14×106 neutron cm-2s-1, epitermal 1,18×106 neutron cm-2s-1, dan neutron cepat 3,37×106 neutron cm-2s-1. Hasil pengukuran spektrum tersebut mengkonfirmasi bahwa terjadi penurunan fluks neutron termal di ujung tabung berkas neutron radiografi (dari 9,2×106 neutron cm-2s-1), sehingga hal ini bisa menjadi salah satu sebab penurunan kualitas ketajaman citra radiografi.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"52 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-08-23","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"83782565","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"ANALYSIS ON AlMg2 AS RSG-GAS CLADDING MATERIAL CORROSION IN CHLORIDE CONTAINING WATER","authors":"F. Bahar, S. Sriyono, G. R. Sunaryo","doi":"10.17146/gnd.2018.21.2.4271","DOIUrl":"https://doi.org/10.17146/gnd.2018.21.2.4271","url":null,"abstract":"AnalYsis On AlMg2 AS RSG-GAS CLADDING material corrosion IN CHLORIDE CONTAINING WATER. The AlMg2is one of an alluminium alloy that used as cladding material for the RSG GA. Siwabessy (RSG-GAS) research reactor in Serpong, Indonesia. The reactor uses demineralized water as primary coolant with 6.5 to 7.5 of pH. A poor treatment of water in primary coolant can lead to the problem of AlMg2 integrity. The primary coolant concentration of chloride must lower than 0.0094 ppm to protect cladding corrosion. The purpose of this study is to determine the effect of temperature and chloride ion concentration to AlMg2. The method in this research is to observe the corrosion rate for AlMg2 material by using Potentiostat. The laboratory experiments were conducted in various temperatures (28, 35, 40 and 45°C) and concentration of sodium chloride of 0.005, 0.010, 0.015, 0.020, 0.025, 0.030 and 0.035 ppm. The results show the corrosion rates were very small, and the highest corrosion rate occurred is 1.23 x 10-3mpy in 0.035 ppm of NaCl at 45°C .","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"1 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"87230877","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

{"title":"NEUTRONIC ANALYSIS ON IRRADIATION OF THE LEU ELECTROPLATING TARGET IN THE RSG-GAS REACTOR FOR PRODUCTION OF 99MO RADIONUCLIDE","authors":"S. Pinem, T. M. Sembiring, T. Tukiran, Ik Iman Kuntoro","doi":"10.17146/gnd.2018.21.2.4392","DOIUrl":"https://doi.org/10.17146/gnd.2018.21.2.4392","url":null,"abstract":"RSG-GAS reactor is a research reactor operated for radioisotope production, neutron activation analysis, research material testing, industry demand, R & D institutions and universities. One of the routine activities performed for RSG-GAS reactor operation is irradiation of LEU targets into the core to produce 99Mo radionuclide. The target insertion in the core will change the neutronic characteristic of the core so it can exceed the safety limits of reactor operation. This paper analyzes the neutronic parameters due to the insertion of the LEU electroplating target into the reactor core irradiation facility. The neutronic parameters for optimizing the LEU electroplating irradiated target are important for the safety of the reactor operation. Neutronic parameter calculations were performed using WIMS/D5 and Batan-3DIFF codes routinely used for RSG-GAS core calculations. Based on calculations by irradiating the LEU electroplating target in a CIP irradiation position of 36 g causes a reactivity change of 597.724 pcm and a maximum radial power peaking factor of 1.3078. Both of these quantities are within the limits permitted for the safety of the reactor operation.","PeriodicalId":32551,"journal":{"name":"Ganendra Majalah IPTEK Nuklir","volume":"19 1","pages":""},"PeriodicalIF":0.0,"publicationDate":"2018-07-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"86985206","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}