Theoretical and Experimental Analysis of Sodium Cooled Nuclear Reactor Nozzle Loaded by Thermal Shocks
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Date
1975
Authors
Advisors
Journal Title
Series/Report No.
G - Structural Analysis of Steel Reactor Pressure Vessels
G1 - Stress and Strain Analysis of Reactor Pressure Vessels
SMiRT 3 - London, UK. 1975
G1 - Stress and Strain Analysis of Reactor Pressure Vessels
SMiRT 3 - London, UK. 1975
Journal ISSN
Volume Title
Publisher
IASMiRT
