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논문 기본 정보

자료유형
학술저널
저자정보
Khorshidi Abdollah (Gerash University of Medical Sciences Gerash Iran)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제55권 제5호
발행연도
2023.5
수록면
1,871 - 1,877 (7page)
DOI
10.1016/j.net.2023.02.013

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The main goal of the coordinated project development of therapeutic radiopharmaceuticals of Y-90 and Re-188 is to exploit advancements in radionuclide production technology. Here, direct and indirect production methods with medium reactor and cyclotron are compared to evaluate derived neutron flux and production yield. First, nano-sized 186W and 89Y specimens are suspended in water in a quartz vial by FLUKA simulation. Then, the solution is irradiated for 4 days under 9Eþ14 n/cm2/s neutron flux of reactor. Also, a neutron activator including three layersdlead moderator, graphite reflector, and poly ethylene absorbentd is simulated and tungsten target is irradiated by 60 MeV protons of cyclotron to generate induced neutrons for 188W and 90Sr production via neutron capture. As the neutron energy reduced, the flux gradually increased towards epithermal range to satisfy (n/2n,g) reactions. The ob tained specific activities at saturation were higher than the reported experimental values because the accumulated epithermal flux and nano-sized specimens influence the outcomes. The beta emitters, which are widely utilized in brachytherapy, appeal an alternative route to locally achieve a rational yield. Therefore, the proposed method via neutron activator may ascertain these broad requirements.

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