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- [3] Interaction of UO2 and zircaloy during the Chernobyl accident SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XX, 1997, 465 : 1313 - 1318
- [6] STEAM OXIDATION OF UO2 AT HIGH TEMPERATURES AMERICAN CERAMIC SOCIETY BULLETIN, 1968, 47 (04): : 413 - &
- [10] Melting Temperatures and Thermal Conductivities of Corium Prepared from UO2 and Zircaloy-2 ACTINIDES AND NUCLEAR ENERGY MATERIALS, 2012, 1444 : 91 - 96