Preliminary analysis of the structural effects due to dynamic loads of the isolated next generation lead cooled reactor
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Date
2009-08-09T00:00:00+00:00
Authors
Advisors
Journal Title
Series/Report No.
10 - Challenges of New Reactors
10-2 - Experimental Simulation, Code Application and Engineered Safety
SMiRT 20 - Espoo (Helsinki), Finland. August 9-14, 2009
10-2 - Experimental Simulation, Code Application and Engineered Safety
SMiRT 20 - Espoo (Helsinki), Finland. August 9-14, 2009
Journal ISSN
Volume Title
Publisher
IASMiRT
