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Development of 99Mo/99mTc Generator System for Production of Medical Radionuclide 99mTc using a Neutron-activated 99Mo and Zirconium Based Material (ZBM) as its Adsorbent

Atom Indonesia · Vol. 42 No. 3 (2016) · hlm. 115–121

DOI
10.17146/aij.2016.531
ISSN
2356-5322, 0126-1568
Terbit
2016-12-13
Penerbit
National Research and Innovation Agency
Bahasa
eng
Lisensi
creativecommons.org/licenses/by-nc-sa/4.0

Abstrak

Molybdenum produced from fission of U-235 is the most desirable precursor for 99Mo/99mTc generator system as it is non-carrier added and has high specific activity. However, in the last decade there has been short supply of 99Mo due to several constrains. Therefore, there have been many works performed for development of 99Mo/99mTc generator system using 99Mo which is not produced from either LEU or HEU. This report deals with development of 99Mo/99mTc generator system where zirconium-based material (ZBM) is used as adsorbent of neutron-activated 99Mo. The system was prepared by firstly irradiating natural Mo in the G. A. Siwabessy reactor to produce neutron-activated 99Mo. The target was dissolved in NaOH 4N and then neutralized with 12 M HCl. The 99Mo solution was then mixed with a certain amount of ZBM followed by heating at 90°C for three hours to allow the 99Mo adsorbed on ZBM. The 99Mo-ZBM (9.36 GBq of 99Mo was Mo/ 4.2 g ZBM) was packed on a fritz-glass column. This column was then fitted serially with an alumina column for trapping 99Mo breakthrough. The columns were then eluted daily with saline solution for up to one week. The yield of 99mTc was found to be between 53.7 – 74% (n= 5). All 99mTc eluates were clear solutions with pH of 5. Breakthrough of 99Mo in 99mTc eluates was found to be 0.031 ± 0.019 μCi 99Mo/ mCi 99mTc (n= 5) which was less than the maximum activity of 99Mo allowed in 99mTc solution ( 1 µCi 99Mo/mCi 99mTc). Aluminum breakthrough in 99mTc eluates was found to be less than 10 ppm. The radiochemical purity of 99mTc in form of Na99mTcO4 was 99%. Radiolabeling of this 99mTc towards methylene diphosphonate (MDP) kit gave a radiolabelling efficiency of 99%. In summary, a new 99Mo/99mTc generator system that used neutron-activated 99Mo and ZBM as its adsorbent has been successfully prepared. The 99mTc produced from this new 99Mo/99mTc generator system attained the quality of 99mTc required for medical purposes.Received: 23 Februari 2016; Revised: 13 July 2016; Accepted: 17 July 2016

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  • National Nuclear Energy Agency of Indonesia
  • Padjadjaran University
  • University of Indonesia
  • Japan Atomic Energy Agency
  • Bandung Institute of Technology
  • Indonesia Defense University
  • Syarif Hidayatullah State Islamic University Jakarta
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  • Organisasi berbeda
  • Organisasi sama
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Tampilkan sebagai tabel
Rekan penulisOrganisasiArtikel bersama
K KadarismanNational Nuclear Energy Agency of Indonesia14
Sriyono SriyonoNational Nuclear Energy Agency of Indonesia13
Herlan SetiawanNational Nuclear Energy Agency of Indonesia11
A AbidinNational Nuclear Energy Agency of Indonesia11
Herlina HerlinaNational Nuclear Energy Agency of Indonesia8
H HambaliNational Nuclear Energy Agency of Indonesia3
K. NishikataJapan Atomic Energy Agency3
Siska FebrianaNational Nuclear Energy Agency of Indonesia3
Rohadi AwaludinNational Nuclear Energy Agency of Indonesia3
M. TǎnaseChiyoda Technol Corporation (Japan)3
Kunihiko TsuchiyaJapan Atomic Energy Agency3
Martalena RamliNational Nuclear Energy Agency of Indonesia2
Sunarhadijoso SoenarjoNational Nuclear Energy Agency of Indonesia2
Syulastri EffendiPadjadjaran University1
Anni AnggraeniPadjadjaran University1
Husein Hernandi BahtiPadjadjaran University1
Muhamad Abdulkadir MartoprawiroBandung Institute of Technology1
Titis Sekar HumaniNational Nuclear Energy Agency of Indonesia1
Sandra HermantoSyarif Hidayatullah State Islamic University Jakarta1
Yahdiana HarahapIndonesia Defense University1
Ratna Dini HaryuniNational Nuclear Energy Agency of Indonesia1
Anton BahtiarUniversity of Indonesia1
C.N. ArdiyatnoNational Nuclear Energy Agency of Indonesia1
Veronika Yulianti SusiloNational Nuclear Energy Agency of Indonesia1
D. HaffidNational Nuclear Energy Agency of Indonesia1
Setiawan SetiawanAfiliasi tidak diketahui1
L.B.S. KardonoIndonesian Institute of Sciences1
Arry YanuarUniversity of Indonesia1
Dede KurniasihNational Nuclear Energy Agency of Indonesia1
Anung PujiyantoNational Nuclear Energy Agency of Indonesia1
Rien RitawidyaNational Nuclear Energy Agency of Indonesia1
Mujinah MujinahNational Nuclear Energy Agency of Indonesia1
Witarti WitartiNational Nuclear Energy Agency of Indonesia1
Umi Nur SholikhahNational Nuclear Energy Agency of Indonesia1

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Sumber metadata: OAI-PMH (metadata jurnal) https://atomindonesia.brin.go.id/index.php/aij/oai, pertama di-harvest 8 Nov 2026, terakhir terlihat 8 Nov 2026.
Metadata asli (oai_dc)
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	<dc:title xml:lang="en-US">Development of 99Mo/99mTc Generator System for  Production of Medical Radionuclide 99mTc using a Neutron-activated 99Mo and Zirconium Based Material (ZBM) as its Adsorbent</dc:title>
	<dc:creator>Saptiama, I.</dc:creator>
	<dc:creator>Lestari, E.</dc:creator>
	<dc:creator>Sarmini, E.</dc:creator>
	<dc:creator>Lubis, H.</dc:creator>
	<dc:creator>Marlina, M</dc:creator>
	<dc:creator>Mutalib, A.</dc:creator>
	<dc:subject xml:lang="en-US">99Mo/99mTc generator; Neutron activated Mo; ZBM; 99mTc</dc:subject>
	<dc:description xml:lang="en-US">Molybdenum produced from fission of U-235 is the most desirable precursor for 99Mo/99mTc generator system as it is non-carrier added and has high specific activity. However, in the last decade there has been short supply of 99Mo due to several constrains. Therefore, there have been many works performed for development of 99Mo/99mTc generator system using 99Mo which is not produced from either LEU or HEU. This report deals with development of 99Mo/99mTc generator system where zirconium-based material (ZBM) is used as adsorbent of neutron-activated 99Mo. The system was prepared by firstly irradiating natural Mo in the G. A. Siwabessy reactor to produce neutron-activated 99Mo. The target was dissolved in NaOH 4N and then neutralized with 12 M HCl. The 99Mo solution was then mixed with a certain amount of ZBM followed by heating at 90°C for three hours to allow the 99Mo adsorbed on ZBM. The 99Mo-ZBM (9.36 GBq of 99Mo was Mo/ 4.2 g ZBM) was packed on a fritz-glass column. This column was then fitted serially with an alumina column for trapping 99Mo breakthrough. The columns were then eluted daily with saline solution for up to one week. The yield of 99mTc was found to be between 53.7 – 74% (n= 5). All 99mTc eluates were clear solutions with pH of 5. Breakthrough of 99Mo in 99mTc eluates was found to be 0.031 ± 0.019 μCi 99Mo/ mCi 99mTc (n= 5) which was less than the maximum activity of 99Mo allowed in 99mTc solution ( 1 µCi 99Mo/mCi 99mTc). Aluminum breakthrough in 99mTc eluates was found to be less than 10 ppm. The radiochemical purity of 99mTc in form of Na99mTcO4 was  99%. Radiolabeling of this 99mTc towards methylene diphosphonate (MDP) kit gave a radiolabelling efficiency of 99%. In summary, a new 99Mo/99mTc generator system that used neutron-activated 99Mo and ZBM as its adsorbent has been successfully prepared. The 99mTc produced from this new 99Mo/99mTc generator system attained the quality of 99mTc required for medical purposes.Received: 23 Februari 2016; Revised: 13 July 2016; Accepted: 17 July 2016</dc:description>
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	<dc:contributor xml:lang="en-US">National Nuclear Energy Agency of Indonesia</dc:contributor>
	<dc:date>2016-12-13</dc:date>
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	<dc:source xml:lang="en-US">Atom Indonesia; Vol 42, No 3 (2016): December 2016; 115-121</dc:source>
	<dc:source>2356-5322</dc:source>
	<dc:source>0126-1568</dc:source>
	<dc:source>10.55981/aij.v42i3</dc:source>
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	<dc:rights xml:lang="en-US">Copyright (c) 2016 Atom Indonesia</dc:rights>
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