Prediction of Reactor Pressure Tube Flow Transients with Effects of Friction and Heat Addition Included Using a Fixed-Grid Method of Characteristics
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Date
1975
Authors
Advisors
Journal Title
Series/Report No.
F - Structural Analysis of Reactor Core and Coolant Circuit Structures
F1 - Dynamic Analysis of Reactor Core Structures
SMiRT 3 - London, UK. 1975
F1 - Dynamic Analysis of Reactor Core Structures
SMiRT 3 - London, UK. 1975
Journal ISSN
Volume Title
Publisher
IASMiRT
