Complex FEM based system of computer codes to model nuclear fuel rod thermo-mechanical behavior
No Thumbnail Available
Date
2009-08-09T00:00:00+00:00
Authors
Advisors
Journal Title
Series/Report No.
03 - Applied Computations, Simulations and Animation
03-6 - Heat Transfer & Thermal Hydraulics, Severe Accidents and Non-linear Analysis
SMiRT 20 - Espoo (Helsinki), Finland. August 9-14, 2009
03-6 - Heat Transfer & Thermal Hydraulics, Severe Accidents and Non-linear Analysis
SMiRT 20 - Espoo (Helsinki), Finland. August 9-14, 2009
Journal ISSN
Volume Title
Publisher
IASMiRT
