A Model for Fuel Rod and Tie Rod Elongations in Boiling Water Reactor Fuel Bundles
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Date
1979
Authors
Advisors
Journal Title
Series/Report No.
D - Structural Analysis of Reactor Fuel Elements and Assemblies
D4 - Thermal Reactor Subassembly Analysis
SMiRT 5 - Berlin, Germany. 1979
D4 - Thermal Reactor Subassembly Analysis
SMiRT 5 - Berlin, Germany. 1979
Journal ISSN
Volume Title
Publisher
IASMiRT
