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Transactions of the INDIAN CERAMIC SOCIETY   Vol. 46  1987
Sintering of Uranium Dioxide as a Fuel for Nuclear Reactors-A Review
P. BALAKRISHNA, * T. R. RAMAMOHAN AND P. RAMAKRISHNAN
Pages : 153-161
DOI : 10.1080/0371750X.1987.10822862
Abstract
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.
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