Open AccessMetallurgical tests on zirconium-clad Zr-U alloy plates submitted to Hanford for irradiation. Program 6.1.2a
Author(s) -
S.H. Paine,
J.E. Draley,
William F. Murphy,
F.L. Brown
Publication year - 1949
Language(s) - English
Resource type - Reports
DOI - 10.2172/12467784
Subject(s) - cladding (metalworking) , materials science , alloy , irradiation , zirconium alloy , zirconium , metallurgy , lanthanide , fission products , metal , composite material , nuclear engineering , chemistry , nuclear physics , engineering , ion , physics , organic chemistry