Theoretical and experimental 8ray spectra of burnt reactor fuel elements
Auteur(s):
Ammar A A
Date de publication:
1975
Référence bibliographique:
Theoretical and experimental 8ray spectra of burnt reactor fuel elements By A A Ammarمجلة العلوم الهندسية كلية الهندسة، جامعة الرياضVol 1 no 1 (January 1975) p p 3342Ammar A A
Résumé:
The concentration of 20 fission isotopes in a burnt fissionable material (025 gm UO2) neutron flux equal to 5x 10 11 neutron cm 2 sec as a fuction of irradiation and cooling times are used together with their individual 8ray spectra to build up the complex spectra which should be expected from any fuel element burnt under various conditions At the same time the 8ray spectra was measured experimentally for several capsules containing the same amount of UO2 (025 gm) irradiated in a reactor neutron flux 5x 10 11 n cm 2 sec and experienced various periods of cooling times Calculated and measured 8 ray spectra (keeping all conditions constant) are found to behave similarly and agree with each other The present study could be of use in connection with the nondestructive tests of reactor fuel elements
