Evaluation of the cross section data for the production of positron emitter 68Ga, A diagnostic radionuclide
Sadia Irfan, M. Phil Physics, 2015-2017 Supervised by Dr. Nouman Amjed
Evaluation of the cross section data for the production of positron emitter 68Ga, A diagnostic radionuclide / Sadia Irfan - Lahore : Division of Science & Technology, University of Education, 2018 - xiii, 70 p. CD
The 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.
hbk
Physics--Evaluation--Cross Section Data--Positron Emitter
539.1 / Ev132
Evaluation of the cross section data for the production of positron emitter 68Ga, A diagnostic radionuclide / Sadia Irfan - Lahore : Division of Science & Technology, University of Education, 2018 - xiii, 70 p. CD
The 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.
hbk
Physics--Evaluation--Cross Section Data--Positron Emitter
539.1 / Ev132
