Calculation of the Cross-Section and Neutron Yield for Production Reactions of Gallium-67
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Abstract
The study of cross-section and the neutron Yield of Gallium–67 isotope is a very necessary choice in the field of nuclear medicine, which is used in radiopharmaceuticals and for medical diagnosis and treatments. The cross-section of 68Zn (p,2n) 67Ga, 67Zn (p, n) 67Ga was calculated for different energies by using different sets of programs using MATLAB language. The cross-section was then used to calculate the neutron yields. The results of the neutron yield distributions have been used to generate polynomial expressions with incident proton energies. We also calculated the stopping power through the Ziegler formula using the computer program (SRIM 2013) to calculate the two reactions mentioned above and also compared the results for stopping powers for the above reactions with the computer program (MATLAB 2017). Then, the neutron yield was calculated for these two reactions to find the best reaction with the highest neutron Yield in our study and use it to calculate the isotope production Yield for these reactions and other results within this study.
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References
Audi G.; Wapstra A. Nuclear Physics Appl. Phys. 1995, A595, 4, 409.
Jawad, E.A.; Jassim, M.K.; Tawfeek, H.M. Calculating the Sputtering Yield of Lithium, Sodium and Krypton Bombarded by Same Target Ion Using TRIM Simulation Program. Ibn AL-Haitham Journal For Pure and Applied Science 2017, 29, 3, 26-35. https://doi.org/10.1063/5.0172339.
Meyerhof, W.E. Elements of Nuclear Physics. McGraw–Hill 1967, 22, 174.
Samira, A.E.; Firas, M.H.; Mustafa, K.J.; Huda, M.T. Simulation Study of Sputtering Yield of Zn Target Bombarded by Xenon Ions, Ibn Al-Haitham J. for Pure & Appl. Sci. 2016, 29(2), 12-23. https://doi.org/10.1063/5.0172339.
Mohammed, N.A.; Samira, A.E. Study of Lung Cancer Hazard Due to Radiate Radon Gas for Two Factories in Industrial Region (Shaikh Omar) of Baghdad Governorate. Ibn Al-Haitham Jour. for Pure & Appl. Sci. 2020, 33(4), 34-45. https://doi.org/10.30526/33.4.2522.
James, J.D.; Louis, J.H. Nuclear Reactor Analysis. John Wiley & Sons, Inc. 1975, 12, 234.
Shirokov, M.; Yadin, N. Nuclear Physics. Mir Publisher Moscow 1982, 11, 1244.
Lilley, J. Nuclear physics. John Wiley & Sons, Ltd. 2001, 764.
Shaimaa, A.A.; Seham, H.S.; Samira, A.E.; Huda, M.T. Investigation of the Nuclear Structure of Some Ni and Zn Isotopes with Skyrme Hartree-Foc. Baghdad Science Journal, 2022, 19(4), 914-921. http://dx.doi.org/10.21123/bsj.2022.19.4.0914.
Burcham, W.E.; Jobes, M. Nuclear and particles physics. Books. Org. 1994, 2343.
Arora, E.D. Dictionary of Physics. Low Textbook Publishers, Delhi, India. 2003, 2244.
Mohammed, N.A.; Ebrahiem, S.A. Assessment of radiation risk parameters for natural radon in three Iraqi institutions for February. AIP Conference Proceedings 2020, 2307, 020003. https://doi.org/10.1063/5.0035396.
Bariq, H.W.; Sameera, A.E. Study of the nuclear properties of an aluminum isotope in the production of third cycle elements. AIP Conference Proceedings 2022, 2437, 020087. https:// doi.org/10.1063/5.0094228.
Hassan, I.M.; Ebrahiem, S.A.; Al-Khafaji, R.S. Calculated the Quadrupole Electrical Transmission |M(E2)|2 W.u For Even-Even Nuclides of Strontium (78-100Sr and 66-76Ge). AIP Conference Proceedings 2022, 2437, 020114. https://doi.org/10.1063/5.0094215.
Knoll, G.F.; Radiation detection and measurement. 2nd and 3rd. wiley, New York 1989, 23002.
Washington, D.C. International commission on radiation units and measurements. USA 1970.
Ebrahiem, S.A.; Falih, E.H.; Mahdi, H.A.; Shaban, A.H. Indoor 222Rn measurement and hazards indices in houses of Al-Najaf province Iraq. AIP Conference Proceedings, 2018, 030003.
https:// doi.org/10.1063/1.5039190.
Ziegler, J.F.; Helium: Stopping Powers and Ranges in all elemental Matter. Peramon Press Oxford 1977, 23(3),123-134.
Wrean, P.R.; Kavanagh, R.W. The cross-section of this reaction was measured for alpha energy (2.2841-3.0999) MeV for 19 F(α,n)22Na J, PR/C,62,055805, Appl. Phys. 2000, 12(2), 34-44. https://doi.org/10.1103/PHYSREVC.62.055805.
Anderson, M.; Kennett, S.J. Nuclear Physics. Sec. A, 1979, 318, 471.
Norman, E.; Chupp, T.J.; Nuclear Physics. Sec. A, 1982, 390, 561.
Ziegler, J.F.; Biersack, J.P.; Littmark, U. the stopping and range of ions in solids. Pergamon Press, New York. 1985. 12(32), 44-56. https://doi.org/10.1007/978-3-642-68779-2_5.
Trim, V.; Ziegler, J.F.; Biersack, J P. Updated version of a computer code for calculating stopping and Ranges, described in Reference, Appl. Physics. 2003. 12(4), 45-56.https://doi.org/10.1016 /J.NIMB.2010.02.091.
Bowler, M. Nuclear physics. Pergamon Press Ltd. Oxford 1973, 232.
Pupillo, G.; Sounalet, G.; Methods in Physics. Journal Nuclear Instruments. Res. Sect. B. 2018, 415(41), 23-44. https://doi.org/10.1016/J.NIMB.2017.10.022.
Szelecsenyi, F.; Steyn, G.F.; Methods in Physics Res., Sect. B. Journal Nuclear. Instrument 2005, 234 (4), 12-34. https://doi.org/10.1016/J.NIMB.2009.03.097.
Szelecsenyi, F.; Kovacs, Z. Investigation of direct production of 68Ga with low energy multiparticle accelerator.Journal Radio-chemical Acta, Germany. 2012, 100, 5, 34-45. https:// doi.org/10.1524/ract.2011.1896.
Stoll, T.; Kastleiner, S. Excitation functions of proton-induced reactions on 68-Zn from threshold up to 71 MeV, with specific reference to the production of 67-Cu. Journal Radio-chemical Acta, Germany 2002, l9 (309), 33-45. https://doi.org/10.1524/ract.2002.90.6.309.
Szelecsenyi, F.; Boothe, T.E.; Takacs, S. Evaluation of direct production of Ga with high energy multiparticle. Journal Applied Radiation and Isotopes, 1998, 49, 1005, 45-65. https://doi.org /10.1016/S0969-8043%2897%2910103-8.
Hermanne, A. Evaluated cross-section and thick target yield databases of Zn+p processes for practical applications. Journal Applied Radiation and Isotopes 1997, 49, 1005, 23-33. https:// doi.org/10.1016/S0969-8043(97)10103-8.