共 50 条
- [31] HISTORICAL RAIL ACCIDENT ANALYSES IDENTIFYING ACCIDENT PARAMETERS THAT COULD IMPACT TRANSPORTATION OF SPENT NUCLEAR FUEL PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2010, VOL 7, 2010, : 471 - 481
- [32] Recent Development of Code Case on Use of Ductile Cast Iron for Transport and Storage Cask for Spent Nuclear Fuel PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, VOL 7, 2009, : 225 - 233
- [35] Micromechanical aspects of constraint effect in steel for containers of spent nuclear fuel ADVANCES IN MECHANICAL BEHAVIOUR, PLASTICITY AND DAMAGE, VOLS 1 AND 2, PROCEEDINGS, 2000, : 1409 - 1414
- [39] MATERIAL TRANSPORT MODELS FOR ACCIDENT-INDUCED FLOW IN NUCLEAR-FUEL CYCLE FACILITIES TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 50 (NOV): : 465 - 465
- [40] USE OF GEOMETRICALLY-ACCURATE MODELS TO PREDICT SPENT NUCLEAR FUEL CLADDING TEMPERATURES WITHIN A TRUCK CASK UNDER NORMAL AND FIRE ACCIDENT CONDITIONS PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2010, VOL 7, 2010, : 531 - 541