Garuda - Garba Rujukan Digital

All

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

jstni
Website

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 21, No 1 (2020): Februari 2020" : 6 Documents clear

IN VIVO BIODISTRIBUTION OF 99mTc-MDP FOR EARLY OSTEOPOROSIS MONITORING IN OVARIECTOMIZED BALB/C MICE Ahmad Kurniawan; Yulianne Mahesa; Teguh Hafidz Ambar Wibawa; Iswahyudi Iswahyudi; Isti Daruwati; Aang Hanafiah Wangsaatmadja
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 21, No 1 (2020): Februari 2020
Publisher : BATAN

Technetium-99m Methylene Diphosphonate (99mTc-MDP) has been utilized in a variety of clinical situations to identify bone areas due to the strong affinity of hydroxyapatite crystals in the mineral phase of the bone with the diphosphonate compounds. Osteoporosis is a disease characterized by decreased bone mass and increased fracture risk and represents a significant population health issue. It has been observed that 99mTc-MDP can be used for bone scintigraphy especially in case of bone cancer, but biodistribution study of 99mTc-MDP on ovariectomized mice for early monitoring of osteoporosis model remains unclear. Therefore, we aimed to investigate the biodistribution of 99mTc-MDP both in normal and ovariectomized mice. The experiment was performed on BALB/c mice weighing approximately 30 g. Mice were divided into a normal and ovariectomized group. After the first, second and third hours, mice were euthanized using the accepted protocol and the tissue of interest was collected. All tissue and blood were weighed using an analytical scale and counted for radioactivity using Automatic Gamma Counter with NaI(Tl) detector. Administration of 99mTc-MDP showed in normal mice compared with an animal model of osteoporosis, there are significant differences at 1 hour post-injection from (20.32±1.38) %ID/g decreased to (7.42±2.61) %ID/g, 2 hours from (13.75±0.01) %ID/g to (5.25±0.25) %ID/g and 3 hours from (12.18±1.44)%ID/g to (4.86±1.34) %ID/g uptake in the bones with (p<0.05). This study can be a consideration for the clinical application of 99mTc-MDP for early detection of osteoporosis conditions by looking at bone uptake and become a concern in the application for bone scintigraphy if the patient is indicated osteoporosis because it will affect visualization of the organ.

ASSESSING THE OTTO OPTION: THORIUM-CYCLE EXPERIMENTAL POWER REACTOR SPENT FUEL CHARACTERISTICS R. Andika Putra Dwijayanto; Ihda Husnayani; Zuhair Zuhair
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 21, No 1 (2020): Februari 2020
Publisher : BATAN

Two main refuelling option considered for use in a High Temperature Gas-cooled Reactor (HTGR) are multi-pass and once through-then-out (OTTO) cycle. The former possesses superiority in term of fuel utilisation whilst the latter is considered better in term of system simplicity. HTGR-based Experimental Power Reactor (Reaktor Daya Eksperimental/RDE) is supposed to adopt multi-pass refuelling scheme. However, OTTO-scheme shall also be considered for the simplicity it offers and thus potentially lower cost. Due to different neutronic and burnup profile between the two, the resulting spent fuel characteristic is also different and possibly requires different handling mechanism. This paper assesses the characteristics of OTTO-scheme RDE spent fuel using thorium fuel cycle. The assessment is performed employing ORIGEN2.1 code. At day 30 of cooling after determined end-of-cycle (EOC), each spent fuel yields 234.9 Curies of radioactivity, emitting 66.26 neutrons/second, 1x1013 photons/second, and releasing 0.7675 watts of decay heat. These numbers must be taken into consideration regarding spent fuel management and spent fuel cask design. Tl-208 isotope characteristics, whose existence is unique to thorium fuel cycle, were also determined. It is found to be yielding 3.42x10-3 Curie of radioactivity and releasing 1.2x108 photons/second at its peak. Understanding its high-energy gamma release, proper radiation protection mechanism must be implemented.

CALCULATION OF NEUTRON FLUX DISTRIBUTION AT PIERCING BEAM PORTS OF PLATE TYPE RESEARCH REACTOR BANDUNG Epung Saepul Bahrum; Prasetyo Basuki; Alan Maulana; Jupiter Sitorus Pane
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 21, No 1 (2020): Februari 2020
Publisher : BATAN

Based on a strategic plan of TRIGA 2000 Bandung’s future operation, BATAN has already decided to implement an option to convert the fuel elements core of TRIGA 2000 from using the cylindrical type of elements produced by General Atomic to MTR plate type of fuel elements produced by local fuel element manufacture. The core design calculation has proved that the core configurations of 5 x 5 matrix using local plate type fuel elements met the requirement of core neutronics design. In addition to the current core configuration, further study must be added to consider the use of beam ports as utilization facilities in the design. The neutron flux distribution at piercing beam port has been calculated based monte carlo algorithm using TRIGA MCNP and MCNP software. The calculation result showed that at piercing beam port surface neutron flux distribution is not quite symmetric. The highest neutron flux at piercing beam port is , where as the flux of neutron thermal energy group is . These results are considerably appropriate for such core configuration and as a result, they can be used as a basic data for designing Plate Type Research Reactor Bandung, especially for neutron diffraction experiment

PREPARASI SENYAWA ANTI KANKER APIGENIN BERTANDA RADIOIODIUM-131 UNTUK STUDI BIOAKTIVITAS Teguh Hafiz Ambar Wibawa; Eva Maria Widyasari; Iswahyudi Iswahyudi; Ade Suherman; Maula Eka Sriyani; Ahmad Kurniawan; Danni Ramdhani
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 21, No 1 (2020): Februari 2020
Publisher : BATAN

PREPARASI SENYAWA ANTI KANKER APIGENIN BERTANDA RADIOIODIUM-131 UNTUK STUDI BIOAKTIVITAS. Apigenin merupakan senyawa flavonoid yang mempunyai potensi sebagai senyawa anti kanker, anti oksidan, dan anti inflamasi dengan toksisitas intrinsik yang rendah. Untuk mengetahui bioaktivitas apigenin, dapat dilakukan radioiodinasi kemudian dilanjutkan dengan studi praklinis menggunakan hewan uji. Pada penelitian ini dilakukan preparasi apigenin bertanda radioiodium-131 menggunakan metode kloramin-T dan optimasi berbagai parameter serta kondisi penandaan. Hasil optimasi diperoleh formula dan kondisi penandaan yaitu 1 mg apigenin, 250 µg kloramin-T, dan 100 µg natrium metabisulfit, dengan pH penandaan 7 dan jumlah radioiodium-131 10 µL (10 µCi). Proses penandaan senyawa 131I-Apigenin dilakukan melalui reaksi substitusi elektrofilik selama 20 menit pada suhu kamar (20-22 °C). Dari hasil pengujian menggunakan metode kromatografi kertas menggunakan fasa diam Whatman 1 dan fasa gerak amonium asetat 0,02 M, pH 6, diperoleh kemurnian radiokimia sebesar 96,53 ± 1,87%. Hasil tersebut menunjukkan bahwa 131I-Apigenin dapat digunakan untuk studi selanjutnya, yaitu studi fisikokimia dan studi praklinis, sehingga dapat diperoleh karakteristik bioaktivitas dan efektivitasnya sebagai senyawa anti kanker berbasis bahan alam.

PENGARUH DAN KONTRIBUSI PUPUK KANDANG TERHADAP N TOTAL, SERAPAN N (15N), DAN HASIL PADI SAWAH (ORYAZAE SATIVA L.) VARIETAS MIRA-1 Taufiq Bachtiar; Nur Robifahmi; Anggi Nico Flatian; Sudono Slamet; Ania Citraresmini
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 21, No 1 (2020): Februari 2020
Publisher : BATAN

Pupuk organik penting untuk memperbaiki sifat kimia, fisika, dan biologi tanah. Penelitian ini dilakukan untuk mempelajari peran pupuk kandang sapi dalam menyumbangkan nitrogen (N) pada tanaman padi sawah dengan teknik isotop 15N. Penelitian dilakukan di tanah sawah Jayamukti, Karawang Jawa Barat. Penelitian ini menggunakan rancangan acak lengkap dengan 6 perlakuan dan 3 ulangan. Perlakuan yang diberikan adalah pupuk kandang dengan dosis 0 t ha-1, 0 t ha-1 + 300 kg N ha-1, 5 t ha-1 + 300 kg N ha-1, 10 t ha-1 + 300 kg N ha-1, 15 t ha-1 + 300 kg N ha-1, 20 t ha-1 + 300 kg N ha-1. Hasil penelitian menunjukkan bahwa aplikasi pupuk organik dengan dosis 20 t/ha disertai dengan urea 300 kg N ha-1 dapat meningkatkan hasil berat kering gabah secara nyata sebanyak 64,75% dari perlakuan kontrol tanpa pupuk kandang dan tanpa N. Aplikasi pupuk kandang sebesar 15 t ha-1 ditambah N rekomendasi berpengaruh nyata dalam meningkatkan sumbangan N berasal dari tanah pada jerami sebesar 19,98% dari perlakuan tanpa pupuk kandang + N. Penelitian ini menunjukkan bahwa pemberian pupuk kandang mampu meningkatkan sumbangan atau kontribusi hara terutama N yang berasal dari tanah pada tanaman padi sawah.

Cover dan Redaksi, Vol 21, No:1, 2020 - Februari 2020 JSTNI PSTNT BATAN
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 21, No 1 (2020): Februari 2020
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2020.21.1.5978

Page 1 of 1 | Total Record : 6

Filter by Year

2020 2020

Filter By Issues

All Issue Vol 24, No 2 (2023): August 2023 Vol 24, No 1 (2023): February 2023 Vol 23, No 2 (2022): Agustus 2022 Vol 23, No 1 (2022): February 2022 Vol 22, No 2 (2021): Agustus 2021 Vol 22, No 1 (2021): February 2021 Vol 21, No 2 (2020): Agustus 2020 Vol 21, No 1 (2020): Februari 2020 Vol 20, No 2 (2019): Agustus 2019 Vol 20, No 1 (2019): Februari 2019 Vol 19, No 2 (2018): Agustus 2018 Vol 19, No 1 (2018): Februari 2018 Vol 18, No 2 (2017): Agustus 2017 Vol 18, No 1 (2017): Februari 2017 Vol 17, No 2 (2016): Agustus 2016 Vol 17, No 1 (2016): Februari 2016 Vol 16, No 2 (2015): Agustus 2015 Vol 16, No 1 (2015): Februari 2015 Vol 15, No 2 (2014): Agustus 2014 Vol 15, No 1 (2014): Februari 2014 Vol 14, No 2 (2013): Agustus 2013 Vol 14, No 1 (2013): Februari 2013 Vol 13, No 2 (2012): Agustus 2012 Vol 13, No 1 (2012): Februari 2012 Vol 12, No 2 (2011): Agustus 2011 Vol 12, No 1 (2011): Februari 2011 Vol 11, No 2 (2010): Agustus 2010 Vol 11, No 1 (2010): Februari 2010 Vol 10, No 2 (2009): Agustus 2009 Vol 10, No 1 (2009): Februari 2009 Vol 9, No 2 (2008): Agustus 2008 Vol 9, No 1 (2008): Februari 2008 Vol 8, No 2 (2007): Agustus 2007 Vol 8, No 1 (2007): Februari 2007 Vol 7, No 2 (2006): Agustus 2006 Vol 7, No 1 (2006): Februari 2006 Vol 6, No 2 (2005): Agustus 2005 Vol 6, No 1 (2005): Februari 2005 Vol 5, No 2 (2004): Agustus 2004 Vol 5, No 1 (2004): Februari 2004 Vol 4, No 4 (2003): Agustus Edisi Khusus 4 2003 Vol 4, No 3 (2003): Agustus Edisi Khusus 3 2003 Vol 4, No 2 (2003): Agustus Edisi Khusus 2 2003 Vol 4, No 1 (2003): Agustus Edisi Khusus 1 2003 Vol 4, No 1 (2003): Februari 2003 Vol 3, No 2 (2002): Agustus 2002 Vol 3, No 1 (2002): Februari 2002 Vol 2, No 2 (2001): Agustus 2001 Vol 2, No 1 (2001): Februari 2001 Vol 1, No 2 (2000): Agustus 2000 Vol 1, No 1 (2000): Februari 2000 More Issue

Home Page

OAI Link

Editorial Team

Contact

Reviewer

Google Scholar

Contact Name
-

Contact Email
-

Phone
-

Journal Mail Official
jstni_batan@batan.go.id

Editorial Address
PSTNT BATAN Bandung Jalan Tamansari 71

Location
Kota adm. jakarta selatan,

Dki jakarta

INDONESIA

Abstract

Abstract

Abstract

Abstract

Abstract

Abstract

Home Page

OAI Link

Editorial Team

Contact

Reviewer

Google Scholar

Contact Name -

Contact Email -

Phone -

Journal Mail Official jstni_batan@batan.go.id

Editorial Address PSTNT BATAN Bandung Jalan Tamansari 71

Location Kota adm. jakarta selatan, Dki jakarta INDONESIA

Abstract

Abstract

Abstract

Abstract

Abstract

Abstract

Contact Name
-

Contact Email
-

Phone
-

Journal Mail Official
jstni_batan@batan.go.id

Editorial Address
PSTNT BATAN Bandung Jalan Tamansari 71

Location
Kota adm. jakarta selatan,

Dki jakarta

INDONESIA