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Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology)

jstni
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Published by Badan Tenaga Nuklir Nasional

ISSN : 14113481 EISSN : 25031287 DOI : https://search.crossref.org/?q=%22jurnal+sains+dan

Core Subject : Health, Science, Social, Engineering,

Biochemistry, Genetics & Molecular Biology Energy Environmental Science Materials Science & Nanotechnology Mechanical Engineering Medicine & Pharmacology Physics

Focus of Publication in Indonesian Journal of Nuclear Science and Technology : Result of experiment in the field of nuclear science and technology and its applications in various fields. Acceptable topics include: Radioisotope, Radiopharmacy, Nuclear Medicine, Nuclear Radiation and its Measurement, Nuclear Physics and Reactors, Nuclear Instrumentation and Radioactive Waste including its applications in the fields of health, biology, industry, agriculture, metallurgy and environment

Arjuna Subject : Kimia(semua kategori) - Kimia (Lain-Lain)

Articles 6 Documents

Search results for , issue "Vol 18, No 2 (2017): Agustus 2017" : 6 Documents clear

PENINGKATAN EFISIENSI PEMISAHAN RADIOISOTOP TERBIUM-161 BERBASIS KROMATOGRAFI KOLOM UNTUK APLIKASI TERAPI KANK Azmairit Aziz
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 18, No 2 (2017): Agustus 2017
Publisher : BATAN

ABSTRAK PENINGKATAN EFISIENSI PEMISAHAN RADIOISOTOP TERBIUM-161 BERBASIS KROMATOGRAFI KOLOM UNTUK APLIKASI TERAPI KANKER. Angka kematian akibat kanker terus meningkat setiap tahun. Endoradioterapi, teknik nuklir menggunakan radionuklida untuk terapi kanker, merupakan teknik yang kompetitif dalam menangani penyakit kanker. Terbium-161 (161Tb) adalah radiolantanida pemancar-β- lemah (Eβ-rata-rata = 0,150 MeV) dan memiliki waktu paro selama 6,9 hari yang potensial untuk terapi kanker ukuran kecil. Pada penelitian sebelumnya telah diperoleh pemisahan 161Tb dari hasil iradiasi bahan sasaran Gd2O3 diperkaya isotop 160Gd dengan metode kromatografi ekstraksi. Akan tetapi yield 161Tb yang diperoleh masih rendah, yaitu ~ 93%. Pada penelitian ini telah dilakukan upaya untuk meningkatkan efisiensi pemisahan 161Tb dari hasil iradiasi bahan sasaran Gd2O3 diperkaya isotop 160Gd menggunakan berbagai ukuran dan jenis resin Ln. Bahan sasaran Gd2O3 diperkaya isotop 160Gd (98,4 %) diiradiasi di RSG-G.A.Siwabessy. Radioisotop 161Tb dipisahkan dari matriks Gd/Tb hasil iradiasi Gd2O3 dengan metode kromatografi ekstraksi menggunakan kolom resin Ln yang memiliki ukuran partikel 20 – 50, 50 – 100 dan 100 – 150 μm serta catridge resin Ln, Ln2 dan Ln3 dengan ukuran partikel 50 – 100 μm sebagai fase diam. Sebagai fase gerak digunakan larutan HNO3 0,8N dan 3N masing-masing untuk memisahkan isotop gadolinium dan terbium. Pada penelitian ini diperoleh peningkatan efisiensi pemisahan 161Tb menggunakan catridge resin Ln dengan ukuran partikel 50 – 100 μm (ditandem 2 buah) dengan yield sebesar 100 ± 0,1% dan Gd recovery sebesar 97,65 ± 0,2%. Radioisotop 161Tb hasil pemisahan memiliki kemurnian radionuklida 99,98 ± 0,01%. Sediaan radioisotop 161TbCl3 yang dihasilkan memiliki kemurnian radiokimia sebesar 99,92 ± 0,2%.

THE ASSESSMENT OF BANDUNG TRIGA REACTOR TANK RADIOACTIVITY IN THE PERIOD 2000-2014 USING ORIGEN-2 Sudjatmi Kustituantini Alfa; Reinaldy Nazar; Ketut Kamajaya; Putranto Ilham Y
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 18, No 2 (2017): Agustus 2017
Publisher : BATAN

THE ASSESSMENT OF BANDUNG TRIGA REACTOR TANK RADIOACTIVITY IN THE PERIOD 2000-2014 USING ORIGEN-2 In accordance with the regulation of the regulatory body of Indonesia related to the decommissioning of nuclear reactors, the management of the Bandung TRIGA reactor have to prepare a decommissioning plan document of the Bandung TRIGA research reactor. Decommissioning program documents shall be regularly updated every five years of the operation of nuclear reactor. In year 2000, Bandung TRIGA reactor tank have been lined using aluminum alloy 6061-T6 and has activated during reactor operation. Aluminum alloy 6061-T6 contains impurities that can produce high radioactivity and has a long half-life. This paper describes the radioactivity of the reactor tank after activation during the period from 2000 to 2014 using the software ORIGEN-2. Total radioactivity of the reactor tank bottom after decay for 5 years was 1.83 10-7 Curie, while the total radioactivity of reactor tank wall was 3.2 10-3 Curie.

PEMBUATAN RADIOIODIDA-131 (131I) BEBAS PENGEMBAN BERDASARKAN KOLOM RESIN AMBERLIT Dara Alfathia; Iwan Hastiawan; Duyeh Setiawan
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 18, No 2 (2017): Agustus 2017
Publisher : BATAN

Saat ini metode yang sering digunakan dalam pembuatan radioiodida-131 (131I) bebas pengemban (carrier-free) yaitu radioisotop tanpa tambahan pengemban (non-carrier-added radioisotopes) adalah menggunakan metode pemisahan distilasi basah atau distilasi kering. Kelemahan metode distilasi diantaranya membutuhkan peralatan yang rumit dan kemungkinan besar terjadi kontaminasi akibat penguapan serta pelepasan 131I. Untuk mengatasi kelemahan metode distilasi dan supaya pengerjaannya sederhana, dikembangkan pemisahan berbasis kolom berisi resin penukar ion (Amberlit). Metode teknik pengocokan terhadap perilaku pertukaran radioiodida-131 dan telurium-130 dalam resin penukar ion di media larutan asam dan basa serta parameter-parameter yang berpengaruh terhadap proses pemisahan seperti kapsitas tukar ion, koefisien distribusi (Kd), waktu kontak dan massa resin Amberlit akan dipelajari. Berdasarkan hasil penelitian didapatkan nilai kapasitas tukar ion 1,15 meq/gram berat basah resin, Kd 130Te dan 131I pada pelarut NaOH 2 M dengan waktu kontak 20 menit adalah 47 mL/g dan 113 mL/g. Persen yield pemisahan 131I diperoleh sebesar 60,70 ± 0,09 % dengan menggunakan resin amberlit sebanyak 2 gram. Radioisotop dalam bentuk kimia Na131I memiliki kemurnian radiokimia sebesar 95,27 ± 0,06 % dan kemurnian radionuklida sebesar 99,5 ± 0,02 %. Hasil uji kualitas Na131I berupa larutan jernih, pH 7, kadar Pb<40 ppm, kadar Te<10 µg/mL, kadar reduktor 0,2844 mg/0,1 mL Na131I.

Cover dan Redaksi, Vol 18, No:2, 2017 - Agustus 2017 Muhamad Basit Febrian
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 18, No 2 (2017): Agustus 2017
Publisher : BATAN

ANALYSIS OF RADIATION SAFETY IN THE NPP SITE IN NORMAL OPERATION CONDITION Pande Made Udiyani; Ihda Husnayani
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 18, No 2 (2017): Agustus 2017
Publisher : BATAN

ANALYSIS OF RADIATION SAFETY IN THE NPP SITE IN NORMAL OPERATION CONDITION. Construction of nuclear power plant (NPP) requires an evaluation of radiation safety which proves that operation of the NPP under normal operating condition and postulated abnormal conditions is safe. Analysis of radiation safety at the NPP site under normal operating condition is required to complete the documents of site analysis and safety analysis. This study is aimed to obtain radiation dose in the environment of the NPPs at Sebagin site in province of Bangka Belitung. The doses were calculated using PC-Cream code. It is assumed that there are three 1000-MWe PWR operating in Sebagin site. Input data required for PC-Cream simulation are routine sourceterm of three 1000MWe-PWRs, meteorological data, and agricultural and animal production, and population distribution. The meteorological data consist of stability frequency of weather for 16 sectors (wind direction) taken from local weather data for 1 year. The data of agricultural and livestock production and population distribution are also taken for 1 year for 16 sectors and 20 radial directions. The results show that the maximum dose from all types of radionuclides and all pathways accepted by adult public around Sebagin site is approximately 0.053 mSv/year to the north direction in the radius of 1 km. This dose is far below the dose limit value of 1 mSv/year or dose constraint of 0.3 mSv/year as public acceptance criteria (BAPETEN). It can be concluded that radiation doses are influenced by activity and type of nuclides sourceterm, reactor layout, meteorological condition, and environmental condition.

IN VIVO INTERACTION OF PROPYLTHIOURACIL WITH SODIUM IODIDE (Na131I) RADIOPHARMACEUTICAL IN RATS (Rattus norvegicus) Isti Daruwati; Iim Halimah; Isa Mahendra; Dwi Deasy F; A. Hanafiah WS
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 18, No 2 (2017): Agustus 2017
Publisher : BATAN

IN VIVO INTERACTION OF PROPYLTHIOURACIL WITH SODIUM IODIDE (Na131I) RADIOPHARMACEUTICAL IN RATS (Rattus norvegicus).. The aim of this research is to determine the effect of propylthiouracil (PTU) treatment to pharmacokinetics interaction and biodistribution profile of Na131I radiopharmaceuticals. Three groups of animal model were used in this experiment, i.e. experimental animals which given PTU for 1 time (onset or A groups), PTU for six days (B Groups) and without treatment (control or C Groups). Pharmacokinetics and biodistribution test were conducted by giving PTU per oral and after 24 hours, continued by giving Na131I solution per oral. In pharmacokinetics test, percentage of injection dose/gram of blood (%ID/g) was calculated to determine the absorption, distribution and elimination half time. In biodistribution test, percentage of injection dose/gram of organs was calculated to determine the accumulation of Na131I in spesific organs. The results showed that the absorption half time of A, B and C groups were 3.14 ± 1.42, 2.49 ± 0.49 and 2.52 ± 0.7 hours, respectively. The distribution half time of A, B and C groups were 10.58 + 5.85, 12.92 + 3.75 and 11.42 + 3.15 hours, respectively. The elimination half time of A, B and C groups were 113.03 + 46.03, 96.57+ 47.76 and 196.71 + 145.21 hours, respectively. Biodistribution test results showed that the accumulation of Na131I in thyroid of A, B and C groups were 1.31 + 0.45, 5.03 + 0.55 and 4.45 + 2.24 % respectively. This research was concluded that PTU treatment cannot alter absorption, distribution and elimination half time Na131I, but the accumulation in thyroid was decrease in A group to control.

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Kota adm. jakarta selatan,

Dki jakarta

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