Transactions of the INDIAN CERAMIC SOCIETY Vol. 46 1987
Sintering of Uranium Dioxide as a Fuel for Nuclear
P. BALAKRISHNA, * T. R. RAMAMOHAN
Pages : 153-161
DOI : 10.1080/0371750X.1987.10822862
UO, is one of the most commonly used nuclear power reactor fuels
today. The sintering process of U02 presented in this article brings
out the special features of uo2 including the effect of nonstoichiometry
and dependence of its defect structure on the sintering atmosphere.
A theoretical basis for U02 sintering has been developed in
the first part of the paper and subsequently its relevance to industrial
practice has been brought out. The effect of variables such as oxygen
to uranium ratio, specific surface area of U02 powder, sintering
temperature and additions on the sinterability of UO, have been
discussed and the optimum conditions for the production of uo2 fuel
have been brought out.