Browsing 1971 - SMiRT 1 - Berlin, Germany by Division

Now showing items 4-23 of 67

Division
B - Power Reactor Development and Structural Mechanics [4]
B0 - Power Reactor Development and Structural Mechanics [4]
C - Fuel and Claddding [26]
C1 - Mathematical-Physical Models for Nuclear Fuels Materials [6]
C2 - Stress and Deformation Analysis of Fuel Element Claddings [7]
C3 - Fuel-Cladding Interaction Effects [7]
C4 - Structural Analysis of Fuel Rods [6]
D - Fuel Elements [25]
D1 - Structural Analysis of Fuel Elements [5]
D2 - Stress Analysis of Graphite Fuel/Moderator Elements-I [7]
D3 - Stress Analysis of Graphite Fuel/Moderator Elements-II [6]
D4 - Pebble Bed Reactor Mechanics [7]
E - Shock and Vibration Analysis of Reactor Components [29]
E1 - Thermal Shock, Pressure Pulse, and Impact Response Analysis [8]
E2 - Dynamics of Fast Reactor Excursion and Containment [7]
E3 - Fuel Rod Vibrations in Parallel Flow [6]
E4 - Reactor Component Vibrations [8]
F - Structural Analysis of Core Support and Coolant Circuit Structures [33]
F1 - Structural Analysis of Reactor Core Support Structures [7]
F2 - Structural Analysis of Miscellaneous Reactor Components [8]

Now showing items 4-23 of 67