Open Access
Mechanical behavior of fast reactor fuel pin cladding subjected to simulated overpower transients
Author(s) -
George Johnson,
C.W. Hunter
Publication year - 1978
Language(s) - English
Resource type - Reports
DOI - 10.2172/6631597
Subject(s) - materials science , cladding (metalworking) , nuclear engineering , composite material , irradiation , fluence , helium , corrosion , nuclear physics , physics , atomic physics , engineering