Open AccessApplication of Hastelloy X in gas-cooled reactor systems
Author(s) -
C.R. Brinkman,
P.L. Rittenhouse,
W.R. Corwin,
J.P. Strizak,
Aage Lystrup,
J.R. DiStefano
Publication year - 1976
Language(s) - English
Resource type - Reports
DOI - 10.2172/7347624
Subject(s) - creep , materials science , helium , alloy , nuclear engineering , ultimate tensile strength , oak ridge national laboratory , metallurgy , nuclear physics , engineering , physics , atomic physics