Feasibility studies on the production of cerium-141 as a radiometry source for use in the characterization of nuclear fuels

Characterization of a nuclear fuel for its uniformity, linear density, concentration of fissile material, total length, local hot spots etc. is usually carried out using passive and active gamma ray assay techniques. 57Co due to its favourable radiation characteristics (T1/2:271.8 days, Eγ: 122 keV (85.5%)) is radionuclide of choice in active gamma assay techniques as an external radiometry source in such applications. The energy of gamma rays emitted, its abundance and the half life are the criterion for the selection of the source used. However, 57Co is to be imported and due to its very high cost and difficulty in procurement, availability of a suitable indigenously produced radiometry source for such applications was a long felt need from the users in the department. 141Ce with an half life of 32.7 d and having comparable gamma emission Er145 keV (100% ) was considered as a possible substitute for imported 57Co source. The feasibility of its production by neutron irradiation and the fabrication of a sealed source for radiometric applications was therefore studied