Proton-produced radionuclides for radiodiagnostic modalities in cancer studies

Kambali, Imam

doi:10.1088/1742-6596/1153/1/012106

Cited by 11 publications

(6 citation statements)

References 21 publications

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“…There have been a limited number of publications related to 67 Ga production yield, though available experimental work and theoretical calculations can be collected for comparisons. As seen in Table 2, this calculated work closely agrees with semi-experimental data [30][31] as well as the MCNPX calculation [20] with differences ranging from 0.13% to 13.66% for proton impurities present during the production depend on the type of cyclotron. energy range between 26 and 14 MeV.…”

Section: Comparison With Published Worksupporting

confidence: 82%

“…In addition, a Matlab code was developed for calculations of the end-ofbombardment (EOB) yields of the investigated nuclear reactions using the stopping power data derived from the SRIM calculations and the excitation functions obtained from the TENDL 2017. The calculation procedures have been described elsewhere [29][30][31][32].…”

Section: Methodsmentioning

confidence: 99%

“…energy range between 26 and 14 MeV. In the semiexperimental work by Takács et al [30] and Szelecsényi et al [31], thick target yields were calculated from their experimental nuclear cross-sections. Therefore, further experimental investigations are required for better comparisons.…”

Section: Comparison With Published Workmentioning

confidence: 99%

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Calculated Radioactivity Yields of Gallium-67 using Matlab Codes

Kambali

2020

jsmi

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In nuclear medicine, gallium-67 (67Ga) is potentially applied for imaging a certain type of tissue. In this investigation, 67Ga is theoretically studied in terms of its potential radioactivity yields at the end of various energetic proton bombardments. Nuclear cross-sections derived from the Talys Evaluated Nuclear Data Library (TENDL) 2017 were used as the input files, while a Matlab code was developed to perform the yield calculations of 67Zn(p,n)67Ga and 68Zn(p,2n)67Ga nuclear reactions to produce 67Ga. Two different targets – enriched 67Zn and natZn targets – were simulated in the calculations. The calculated yields suggested that a maximum of 27.37 MBq/µAh could be achieved when enriched 67Zn target was irradiated with 15-MeV protons, whereas 46.99 MBq/µAh could be generated following a 30 MeV proton bombardment of enriched 68Zn target. Various radioactive gallium impurities, i.e. 63,64,65,66,68,70Ga and stable 69Ga isotope were also expected to be generated mostly via (p,n) and (p,2n) reactions when natZn target was used in the 67Ga production. In contrast, radioactive 66Ga and 68Ga impurities were mainly produced following bombardment of enriched 67Zn and 68Zn targets. This study can be used as a reference for future 67Ga radionuclide production.

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Section: Comparison With Published Worksupporting

confidence: 82%

Section: Methodsmentioning

confidence: 99%

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Calculated Radioactivity Yields of Gallium-67 using Matlab Codes

Kambali

2020

jsmi

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“…Sm, 211 At, and 177 Lu have been conducted  Corresponding author. E-mail address: maiyesni@yahoo.com DOI: https://doi.org/10.17146/aij.2019.930 theoretically and experimentally [13][14][15][16][17][18][19][20][21]. Apart from cyclotron-based radionuclide production, nuclear reactor-based radioisotope production has also been studied elsewhere, including for production of diagnostic and therapeutic radioisotope such as beta-emitting radioisotopes 131 I and 153 Sm [22,23].…”

Section: Introduction mentioning

confidence: 99%

Spectral Comparison of Neutron-Irradiated Natural and Enriched Ytterbium Targets for Lu-177 Production

et al. 2019

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Beta-emitting radioisotope 177 Lu has been suggested for radioimmunotherapy, peptide receptor radionuclide therapy, or another radionuclide therapy due to its excellent properties for destroying cancer cells. In this experimental investigation, natural ytterbium ( nat Yb) and enriched 176 Yb targets were irradiated with thermal neutrons at 1.2×10 14 cm -2 s -1 neutron flux for 95 hours. Using a high-purity germanium (HPGe) detector-based spectroscopy system, the post-irradiated targets were measured and the produced radioisotopes were identified according to their gamma ray emissions. Experimental results indicated that several radioisotopes such as 169 Yb and 175 Yb dominate the post-irradiated nat Yb target, though a relatively weak intensity of 177 Lu was also recorded. In contrast, 177 Lu radioisotope dominates the gamma rays observed in the post-irradiated enriched 176 Yb target following elution with HNO 3 solution. For the first time, evidence is found of 175 Yb impurity in the post-neutron-irradiated enriched 176 Yb 2 O 3 target as a result of 176 Yb(n,2n) 175 Yb nuclear reaction. This work recommends future 177 Lu radioisotope production using enriched 176 Yb 2 O 3 target.

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“…The success of radionuclide production in cyclotrons requires deep understanding of irradiation parameters including proton energy, target preparation, proton beam currents and irradiation time [19]. Direct experiments for obtaining these parameters are time and cost consuming, assuming the expensive cost of cyclotron operation, especially if repeated experiments are required to obtain the right parameter values.…”

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confidence: 99%

Comparison of 192Os(p,n)192Ir and 192Os(d,2n)192Ir Nuclear Reactions for 192Ir Production

et al. 2020

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Ir ) is a radionuclide currently suggested for brachyteraphy. One of the methods employed to produce high purity 192 Ir is by irradiation of Os) target using cyclotron. The success of 192 Ir radionuclide production in cyclotrons requires deep understanding of irradiation parameters, including particle energy, target preparation and thickness, particle beam curent and irradiation time. Therefore, theoretical calculations of the 192 Ir radioactivity yields should be carried out as a preliminary measure for more efficient 192 Ir production. In this study, 192 Ir production was simulated using the SRIM 2013 program to determine the optimum target thickness while the nuclear cross-section data were extracted from TENDL 2017. Two nuclear reactions for 192 Ir production yield calculations were compared, i.e., 192 Os(p,n) 192 Ir and 192 Os(d,2n) 192 Ir. The radioactivity yields for 192 Os(p,n) 192 Ir nuclear reaction was found to be lower than 192 Os(d,2n) 192 Ir reaction. For proton and deuteron energy of 30 MeV, the maximum radioactivity yield was 6.79 GBq for 192 Os(p,n) 192 Ir and 26.14 GBq for 192 Os(d,2n) 192 Ir. Several radionuclide impurities such as 191m Ir, 190 Ir, 191 Os and 189 Re were predicted to be generated during 192 Os(p,n) 192 Ir reaction for proton incident energy between 1 and 30 MeV; meanwhile, 192 Ir, 191m Ir, 193 Os, 193m Ir, 192m Os and 191 Os radionuclides were expected to contaminate during 192 Os(d,2n) 192 Ir reaction for deuteron energy between 1 and 30 MeV. Results of this study can be used as a reference for future 192 Ir radionuclide production when proton or deuteron beams are considered to be employed.

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Proton-produced radionuclides for radiodiagnostic modalities in cancer studies

Cited by 11 publications

References 21 publications

Calculated Radioactivity Yields of Gallium-67 using Matlab Codes

Calculated Radioactivity Yields of Gallium-67 using Matlab Codes

Spectral Comparison of Neutron-Irradiated Natural and Enriched Ytterbium Targets for Lu-177 Production

Comparison of 192Os(p,n)192Ir and 192Os(d,2n)192Ir Nuclear Reactions for 192Ir Production

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