000			02886nam a22001697a 4500
999			_c21833 _d21833
005			20221006165305.0
008			221006b ||||| |||| 00| 0 eng d
020			_ahbk
082			_a539.1 _bEv132
100			_aSadia Irfan, _bM. Phil Physics, _c2015-2017 _dSupervised by Dr. Nouman Amjed
245			_aEvaluation of the cross section data for the production of positron emitter 68Ga, A diagnostic radionuclide _c/ Sadia Irfan
260			_aLahore : _bDivision of Science & Technology, University of Education, _c2018
300			_axiii, 70 p. _eCD
520			_aThe study includes the evaluation of the production data of 68Ga radionuclide, the halflife of its ground state is 68min. It is a potential candidate for diagnostic studies in the field of nuclear medicine; it is gaining importance in the present era, because of its applications as a positron-emitter in Positron Emission Tomography (PET) and Single Photon Emission Computed Tomography (SPECT). Its evaluation leads the optimization of production of 68Ga radionuclide. It is usually produced using generator method using 68Ge/68Ga generator pair but the availability of generator system is limited at commercial level. 68Ga can also be produced using charged particle irradiation using cyclotrons. In this way it can be produced with the vicinity of the hospital. So this work was planned to find out the alternative production possibilities of 68Ga production. In this work we have evaluated total nine reactions namely68Zn(p,n)68Ga,72Ge(p,x)68Ga, 68Zn(d,2n)68 Ga,70Ge(d,α)68Ga, 65Cu(α,n)68Ga, natZn(α,x)68Ga,67Zn(α,x)68Ga, 68Zn(α,x)68Ga and 68 Zn(3He,x)68Ga. For this purpose the compilation of the data was performed using data from EXFOR (online source of IAEA) publications and original thesis. The reliability of the experimental data was cross checked with the results of three nuclear model calculation codes i.e. ALICE-IPPE, EMPIRE and results of TALYS from TENDLE-2015 database. In consistent and wrong values were rejected and not included in the further evaluation. Then the recommended curve of the selected data was gained using the conventional polynomial fitting of the all selected experimental data of a production route. In addition to the fit we have also reported the 95% confidence limit of our recommended values; which is based mainly on the errors in the cross section. Then on the basis of the polynomial fittings a recommended data set will be generated that will be useful for the optimization of a specific production route. In present work, the on-site production routes for 68Ga were considered. 68Ga can be produced at small sized cyclotron using 68Zn(p,n)68Ga reaction and at medium sized cyclotron, the reaction 65Cu(α,n)68Ga appear to be most important production route.
650			_aPhysics--Evaluation--Cross Section Data--Positron Emitter
942			_cTH