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Testing of lithium titanate as an alternate blanket material
註釋This report summarizes the corrosion and hydriding behaviour of zircaloy fuel sheathing irradiated in candu power reactors. destructive examinations of fuel bundles have shown that the sheath oxidation and hydriding that occurs is limited and does not exceed acceptable levels. this is substantiated by the fact that no single fuel failure in any candu power reactor has been directly attributed to corrosion or hydriding. continued excellent fuel performance without corrosion or hydriding problems is expected and ensured with current fuel manufacturing practices and the operating characteristics of candu power reactors.