Analisis Produksi 99Mo Berbasis Waktu Iradiasi Larutan Uranil Nitrat Pada Fasilitas Reaktor Kartini

Puradwi Ismu Wahyono, Syarip

Sari


Abstrak – Selama ini produksi isotop 99Mo sebagai generator 99mTc untuk diagnosis nuklir dalam bidang kedokteran adalah berbasis metode iradiasi 6-days curie. Pada makalah ini disajikan suatu analisis produksi 99Mo berbasis waktu iradiasi target berupa uranil-nitrat (UN), tanpa harus menunggu 6 hari waktu iradiasi. Metode yang digunakan adalah perhitungan pembentukan radioisotop produk fisi dengan bantuan paket program komputer ORIGEN-2. Perhitungan dilakukan untuk sampel ukuran standar volume 0,395 liter dengan variasi waktu iradiasi dan fluks neutron sesuai dengan fleksibilitas operasi reaktor Kartini. Hasil analisis menunjukkan bahwa faktor jam operasi atau waktu iradiasi tidak terlalu signifikan dalam pembentukan 99Mo dibanding faktor variasi fluks neutron. Produksi 99Mo dari sampel standar tersebut pada tingkat fluks neutron maksimum 1012 n/cm2s adalah 1,581 curie, sedangkan total radioaktivitas sampel target UN adalah 168,1 curie.

Kata kunci: produksi isotop, 99Mo, iradiasi, target, uranil-nitrat, fluks neutron, reaktor Kartini

Abstract – So far, the 99Mo isotope production for nuclear diagnosis in the medical field is based on a 6-days curie method. This paper presents a 99Mo production analysis based on the target irradiation time in the form of uranyl-nitrate (UN), without having to wait 6 days of irradiation time. The method used is the calculation of the formation of fission product radioisotopes with the ORIGEN-2 computer code. Calculations were made for a standard sample with a volume of 0.395 liter with variations in irradiation time and neutron flux in accordance with the operating capability of the Kartini reactor. The results of the analysis show that the operating hour or irradiation time factor is not quite significant in the formation of 99Mo compared to the factor of neutron flux variation. The 99Mo production of the standard sample at a maximum neutron flux level of Kartini reactor of 1012 n/cm2s was 1.581 curies, while the total radioactivity of the UN target sample was 168.1 curies.

Key words: isotope production, 99Mo, irradiation, target, uranyl-nitrate, neutron flux, Kartini reactor



Kata Kunci


produksi isotop, 99Mo, iradiasi, target, uranil-nitrat, fluks neutron, reaktor Kartini

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Referensi


Ian Hoffman, Rodney Berg, Medical isotope production, research reactors and their contribution to the global xenon background. Journal of Radioanalytical and Nuclear Chemistry 318 (2018) 165–173.

Eckelman WC. Unparalleled contribution of technetium-99m to medicine over 5 decades. JACC Cardiovasc Imaging 2 (2009) 364–368.

Maroor Raghavan, Ambikalmajan Pillai et al., Sustained availability of 99mTc: possible paths forward, J Nucl Med 54 (2013) 313–323.

International Atomic Energy Agency (IAEA). Homogen-eous Aqueous Solution Nuclear Reactors for the Production of Mo-99 and Other Short Lived Radioisotopes. IAEA TECDOC Report 1601 Vienna, Austria (2008).

Syarip, P. I. Wahyono, W. Susilo and K. Donny, Commissioning preparation of a subcritical experimental facility for 99Mo production, J. Phys. Conf. Ser. 1198 (2019) 022023

Syarip, S. Tegas, B. Edi Trijono, S. Endang, Design and development of subcritical reactor by using aqueous fuel for Mo-99 production. Proceedings of the Pakistan Academy of Sciences: A. Physical and Computational Sciences 55 (2018) 1: 21–26.

Dedy P Hermawan, Rionaldy and Syarip, Neutronic analysis of SAMOP reactor experimental facility using SCALE code system, J. Phys. Conf. Ser. 1090 (2018) 012032.

Syarip, E. Togatorop and Yassar, Molybdenum-99 production calculation analysis of SAMOP reactor based on thorium nitrate fuel, J. Phys. Conf. Ser. 978 (2018) 012072

T. Sutondo, Syarip, Shielding design for the PGNAA experimental facility at Kartini reactor, Journal Atom Indonesia, 44 (2018) 3 : 131-135.

Tegas Sutondo, Syarip, Karakteristik berkas pada beam port tembus dan singgung reaktor Kartini, Majalah Iptek Nuklir GANENDRA 17 (2014) 2: 83-90.

Oak Ridge National Laboratory, RSICC Computer Code Collection ORIGEN 2.2, Oak Ridge National Laboratory, Tennesse (2002).

Edi Trijono Budisantoso, Syarip, Studi produksi radioisotop Mo-99 dengan bahan target larutan uranil nitrat pada reaktor Kartini, Majalah Iptek Nuklir GANENDRA 5 (2002) 1: 1-8.

M. Iqbal Farezza W and Syarip. Mo-99 isotope production calculation of SAMOP reactor experimental facility, J. Phys. Conf. Ser. 1090 (2018) 012013.

L. Wahid, M. I. Farezza W, Syarip, Source term analysis of SAMOP reactor experimental facility, J. Phys. Conf. Ser. 1090 (2018) 012031.

P. I. Wahyono and Syarip, Analysis of uranyl nitrate hexahydrate composition for optimum neutron multiplication factor of SAMOP, J. Phys. Conf. Ser. 1402 (2019) 044071

Artem V. Matyskin, et.al. Feasibility study for production of 99mTc by neutron irradiation of MoO3 in a 250 kW TRIGA, 298 (2013) J Radioanal Nucl Chem 1: 413-418.




DOI: https://doi.org/10.35895/rf.v4i1.172

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