共 50 条
- [1] DENSITY AND MICROSTRUCTURE CHANGES IN UO2 FUEL THROUGH 3 CYCLES OF PWR IRRADIATION AMERICAN CERAMIC SOCIETY BULLETIN, 1979, 58 (03): : 389 - 389
- [4] PERFORMANCE OF STAINLESS-STEEL-CLAD UO2 FUEL ELEMENTS IN BORATED PWR LOOP TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1964, 7 (01): : 120 - &
- [5] IRRADIATION BEHAVIOR OF TUBULAR UO2 FUEL ELEMENTS AMERICAN CERAMIC SOCIETY BULLETIN, 1965, 44 (03): : 221 - &
- [7] IRRADIATION-INDUCED VOLUME CHANGES IN UO2 FUEL AMERICAN CERAMIC SOCIETY BULLETIN, 1974, 53 (04): : 366 - 366
- [8] MODELING THE IRRADIATION SWELLING OF UO2 AT THE FUEL PELLET RIM PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 1, 2014,