
A STUDY OF THE FUEL VALUE OF U{sup 23){sup 3}
Author(s) -
S. Jaye,
L.L. Bennett,
M.P. Lietzke
Publication year - 1960
Language(s) - English
Resource type - Reports
DOI - 10.2172/4156692
Subject(s) - uranium , value (mathematics) , uranium 235 , fuel cycle , radiochemistry , yankee , chemistry , physics , nuclear physics , waste management , neutron temperature , neutron , mathematics , engineering , statistics , art , art history
The fuel value of U/sup 233/ was calculated for five thermal reactors (Dresden. Yankee, Carolinas-Vlrginia, Hallam, GCR-II). Relative to a U/sup 235/ value of per gram, pure U/sup 233/ had a value that varied from .2 to .2 per gram. U/sup 233/ contained in once- and twice-recycle uranium from an initial U/sup 233/-Th cycle had a value slightly in excess of the value of pure U/ sup 233.. The value of U/sup 233/ in recycle uranium from an initial U/sup 235/- Th cycle was less than that for pure U/sup 233/ and decreased with each succeeding cycle. (auth