The purpose of this study is to accumulate and calculate the experimental cross section data
for the production of medically attractive radioisotope 123I. It is suitable longer lived
(T1/2=13.22h) gamma emitter radionuclide which can possibly have applications in the
diagnosis of thyroid cancer as well as can be used for the quantification of the tumors using
PET. The production routes natSb(α,x)123I, natSb(3he,x)123I, 121Sb(α,2n)123I, 123Sb(α,4n)123I,
123Sb(3he,3n)123I, natTe(d,x)123I, natTe(p,x)123I, 122Te(d,n)123I, 123Te(d,2n)123I, 123Te (p,n)123I,
124Te (d,3n)123I, 124Te (p,2n)123I, 125Te (p,3n)123I and 126Te (p,4n)123I have to evaluated and
examined for the production of 123I. The experimental nuclear reaction cross section data
were obtained via the digital library (EXFOR, IAEA-database) and online literature
sources. The experimental data were normalized with the help of monitor reactions and
decay data. The nuclear reaction cross section data were evaluated on the basis of
experimental confident limits and with the weight age of nuclear model codes ALICEIPPE, TENDL and EMPIRE. After these calculations inconsistent data sets were rejected
then polynomial fitting was applied on the selected normalized dat. Finally we generate the
recommended curve. All the production routes were critically analyzed and compared with
each other. Eventually we concluded that 124Te (p,2n)123I reaction is the best production
route.
Key Words: 123I data, PET, evaluation, cross section, EXFOR