1979•Transactions of the American Nuclear SocietyRequires access

Comparison of in-reactor and out-of-reactor fuel pin cladding strain under transient loading

D.R. Duncan, C.W. Hunter, J.R. Thielges, T. Hikido, Jeff Hanson

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Key concepts: Cladding (metalworking), Nuclear engineering, Transient (computer programming), Materials science, Composite material, Engineering, Computer science, Operating system

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Comparison of in-reactor and out-of-reactor fuel pin cladding strain under transient loading — Research Paper | ScholarLens