共 50 条
- [32] HOW TO ACCOMMODATE HIGHER BURN-UP WITHOUT REPLACING YOUR SPENT FUEL SHIPPING FLASKS NUCLEAR ENGINEERING INTERNATIONAL, 1993, 38 (463): : 45 - 47
- [33] Radionuclide release from spent MOX fuel SCIENTIFIC BASIS FOR NUCLEAR WASTE MANAGEMENT XXI, 1998, 506 : 923 - 924
- [35] How good is fuel modelling at extended burn-up? NUCLEAR ENGINEERING INTERNATIONAL, 1997, 42 (518): : 32 - &
- [37] Direct burn-up determination of fast reactor mixed oxide (MOX) fuel by preferential evaporation of interfering elements Journal of Radioanalytical and Nuclear Chemistry, 2017, 311 : 1593 - 1603