a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods /
prepared by G.A. Berna ... [et al] ; prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
|Related Names:||Berna, Gary A.|
Washington, D.C. : The Commission : 1981.
Nuclear fuel claddings
Nuclear fuel claddings /
Nuclear fuel rods > Nuclear fuel rods / Data processing.
"NRC FIN no. A6050, B2043."
"Date published: January 1981."
"Pacific Northwest Laboratory."
"EG&G Idaho, Inc."
x, 282 p. :
|Locate a Print Version:||
Find in a library
|Item Link||Original Source|
|Full view||University of Michigan|