Design optimization of a new homogeneous reactor for medical radioisotope Mo-99/Tc-99m production

Liem, Peng Hong; Tran, Hoai-Nam; Sembiring, Tagor Malem

doi:10.1016/j.pnucene.2014.07.040

Cited by 22 publications

(11 citation statements)

References 4 publications

Supporting

Mentioning

Contrasting

Unclassified

Order By: Relevance

“…Penggunaan LEU bertujuan untuk mengurangi potensi adanya isu proliferasi atau penggunaan energi nuklir yang mengancam keamanan secara global. Hingga tahun 2011, setidaknya ada 7 (tujuh) reaktor penelitian memasok 99 Mo untuk memenuhi lebih dari 95 % pasokan global untuk aplikasi kedokteran nuklir antara lain (1) NRU-Kanada, (2) HFR-Belanda, (3) BR-2-Belanda, (4) Safari-1-Afrika Selatan, (5) Osiris-Perancis, (6) Maria-Polandia, (7) OPAL-Australia [4,5] . Gangguan pasokan 99 Mo secara global meresahkan sebagian kalangan seperti pemerintah, rumah sakit, dokter maupun pasien yang berkaitan dengan penggunaan 99m Tc sebagai diagnosis, meskipun rantai pasokan 99 Mo masih stabil untuk sementara waktu.…”

Section: Pendahuluanunclassified

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc)

Saptiama

Herlina

Sriyono

et al. 2016

urania

View full text Add to dashboard Cite

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc). Pembatasan penggunaan uranium sebagai target untuk produksi 99mTc menyebabkan rumah sakit di Indonesia kesulitan mendapatkan pasokan 99mTc. Saat ini 99mTc diperoleh dari 99Mo hasil fisi (pembelahan uranium). Pembuatan radionuklida 99Mo dari aktivasi neutron molibdenum alam (MoO3) di teras reaktor G.A Siwabessy digunakan sebagai metode alternatif untuk memperoleh 99mTc. Tujuan penelitian ini adalah untuk melakukan pembuatan radionuklida 99Mo dari aktivasi neutron molibdenum alam untuk memperoleh 99mTc. Serbuk MoO3 alam sebanyak 5 gram dikemas dalam ampul kuarsa dan dimasukkan ke dalam inner capsul selanjutnya dikemas menggunakan outer capsul sebagai bahan target. Bahan target diiradiasi di reaktor G.A Siwabessy selama 100 jam. Hasil perhitungan diperoleh aktivitas 99Mo sebesar 65 % dari nilai maksimum yang dapat diperoleh. MoO3 paska iradiasi dilarutkan dengan NaOH 4 M sehingga diperoleh larutan natrium molibdat (Na2MoO4). Radionuklida 99Mo dan 99mTc diukur menggunakan spektrometer gamma. Radionuklida 99Mo terdeteksi dalam produk larutan Na2MoO4 dengan aktivitas jenis 99Mo yang diperoleh sebesar 0,81 Ci 99Mo/g Mo. Radionuklida anak luruh 99mTc dipisahkan dari radionuklida induk 99Mo menggunakan kolom pemisah yang berisi material berbasis zirkonium (MBZ) sebagai penyerap 99Mo. Radionuklida 99mTc hasil pemisahan diperoleh dalam bentuk natrium pertehnetat (Na99mTcO4).dengan recovery yang masih rendah yaitu sekitar 52 hingga 71 %.Kata kunci: Molibdenum, teknesium, radionuklida, pemisahan, iradiasi. PRODUCTION OF ACTIVATED NEUTRON MOLYBDENUM-99 (99Mo) RADIONUCLIDE FROM NATURAL MOLYBDENUM TO OBTAIN TECHNETIUM-99m (99mTc). Uranium usage restriction causes the hospitals in indonesia difficult to obtain the suply of 99mTc. At Present, 99mTc is obtanied from molybdenum as a uranium fission product. Production of 99Mo radionuclide resulted from neutron activated natural molybdenum (MoO3) in G.A Siwabessy reactor could be used as a alternatif method for producing 99mTc. The aim of this research is synthesize of 99Mo radionuclide from neutron activated natural molybdenum (MoO3) to obtain 99mTc. The five grams of MoO3 powder was packed in a quartz ampule and inserted into inner capsule then also inserted into outer capsule as a target material. It was iradiated in G.A Siwabessy reactor for 100hours. Based on theoritical calculation, about 65 % of maximum 99Mo activity could be recovered. After Irradiation, MoO3 was dissolved by NaOH 4 M solution so it was natrium molybdate (Na2MoO4) solution. 99Mo and 99mTc radionuclide were analyzed using gamma spectrometer. 99Mo radionuclide was detected on Na2MoO4 solution as product that had specific activity of 0.81 Ci 99Mo/ g Mo. 99mTc as daughter radionuclide was separated from 99Mo as parent radionuclide using separated column containing zirconium based material (ZBM) as 99Mo adsobent. 99mTc radionuclide has been succesfully separated using ZBM column although recovery of 99mTc was quite low in which approximately 52 to 71 %. The 99mTc radionuclide was recovered in the form of sodium pertechnetate (NaTcO4) solution.Keywords: Molybdenum, technetium, radionuclide, separation, irradiation.

show abstract

Section: Pendahuluanunclassified

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc)

Saptiama

Herlina

Sriyono

et al. 2016

urania

View full text Add to dashboard Cite

show abstract

“…They also provide the comparison with other charged particle induced production routes and the possible use of the 197g,195m,193m Hg and 196m,196g Au reactions for monitoring deuteron beam parameters. Liem et al [13] propose a conceptual design of a homogeneous solution reactor for production of 99 Mo/ 99m Tc medical radioisotope. Lebedev et al [14] consider possible ways for production of 173 Lu and usages of other radioactive nuclides as radiation sources for crack detectors in gamma defectoscopes.…”

Section: Introductionmentioning

confidence: 99%

Medical Radioisotope Production in a Power-Flattened ADS Fuelled with Uranium and Plutonium Dioxides

Bakır

Selçuklu

Yapıcı

2016

Science and Technology of Nuclear Installations

View full text Add to dashboard Cite

This study presents the medical radioisotope production performance of a conceptual accelerator driven system (ADS). Lead-bismuth eutectic (LBE) is selected as target material. The subcritical fuel core is conceptually divided into ten equidistant subzones. The ceramic (natural U, Pu)O2fuel mixture and the materials used for radioisotope production (copper, gold, cobalt, holmium, rhenium, thulium, mercury, palladium, thallium, molybdenum, and yttrium) are separately prepared as cylindrical rods cladded with carbon/carbon composite (C/C) and these rods are located in the subzones. In order to obtain the flattened power density, percentages of PuO2in the mixture of UO2and PuO2in the subzones are adjusted in radial direction of the fuel zone. Time-dependent calculations are performed at 1000 MW thermal fission power (Pth) for one hour using the BURN card. The neutronic results show that the investigated ADS has a high neutronic capability, in terms of medical radioisotope productions, spent fuel transmutation and energy multiplication. Moreover, a good quasiuniform power density is achieved in each material case. The peak-to-average fission power density ratio is in the range of 1.02–1.28.

show abstract

“…Nevertheless, the separation of 99 Mo fission product is a complex processing technology which is highly costly and also generates large quantities of high-radiotoxicity and long-life radioactive waste and requires extensive purification prior to use. Furthermore, there are few suppliers of 99 Mo fission product from both high-and low-enriched uranium (HEU/LEU) targets available in the world [4,16,17].…”

Section: Introduction mentioning

confidence: 99%

The Use of Sodium Hypochlorite Solution for (n,γ)<sup>99</sup>Mo/<sup>99m</sup>Tc Generator Based on Zirconium-Based Material (ZBM)

et al. 2015

View full text Add to dashboard Cite

]molybdate was then packed into generator column, then eluted with 10 × 1 mL of saline followed by 1 × 5 mL of NaOCl solution. The NaOCl solution concentrations used were 0.5%; 1%; 3%; and 5% for each column, respectively. This study resulted in a ZBM which has a 99 Mo adsorption capacity of 167.5 ± 3.4 mgMo/g ZBM, as well as in a yield eluate of 99m Tc of up to 70%, and the find that the optimum NaOCl concentration was 3%. The use of sodium hypochlorite solution affected 99 Mo breakthrough. The higher sodium hypochlorite concentration used, the more 99 Mo breaktrough exist on 99m Tc eluate.

show abstract

Design optimization of a new homogeneous reactor for medical radioisotope Mo-99/Tc-99m production

Cited by 22 publications

References 4 publications

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc)

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc)

Medical Radioisotope Production in a Power-Flattened ADS Fuelled with Uranium and Plutonium Dioxides

The Use of Sodium Hypochlorite Solution for (n,γ)<sup>99</sup>Mo/<sup>99m</sup>Tc Generator Based on Zirconium-Based Material (ZBM)

Contact Info

Product

Resources

About

Design optimization of a new homogeneous reactor for medical radioisotope Mo-99/Tc-99m production

Cited by 22 publications

References 4 publications

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc)

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc)

Medical Radioisotope Production in a Power-Flattened ADS Fuelled with Uranium and Plutonium Dioxides

The Use of Sodium Hypochlorite Solution for (n,&gamma;)<sup>99</sup>Mo/<sup>99m</sup>Tc Generator Based on Zirconium-Based Material (ZBM)

Contact Info

Product

Resources

About

The Use of Sodium Hypochlorite Solution for (n,γ)<sup>99</sup>Mo/<sup>99m</sup>Tc Generator Based on Zirconium-Based Material (ZBM)