Open AccessIn-reactor rupture testing of Zircaloy-2 clad seven-rod cluster fuel elements: Interim report
Author(s) -
R.L. Call,
J.W. Green,
D.C. Kaulitz
Publication year - 1960
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/10151592
Subject(s) - nuclear engineering , nuclear fission product , cladding (metalworking) , materials science , zirconium alloy , shearing (physics) , fuel element failure , structural engineering , fission products , composite material , forensic engineering , metallurgy , nuclear reactor core , engineering , zirconium