Prediction of Thermal, Mechanical, and Fission Gas Behavior of Carbide Fuel Element During Fast Thermal Transients Using the UNCLE-TUBE Code
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Date
1979
Authors
Advisors
Journal Title
Series/Report No.
C - Analysis of Reactor Fuel and Cladding Materials
C1-2 - Fuel and Fission Product Behavior II
SMiRT 5 - Berlin, Germany. 1979
C1-2 - Fuel and Fission Product Behavior II
SMiRT 5 - Berlin, Germany. 1979
Journal ISSN
Volume Title
Publisher
IASMiRT