The manufacture of the graphite-urania fuel matrix for TREAT /
by J.H. Handwer and R.C. Lied.

Description

Main Author: Handwerk, J. H.
Related Names: Lied, R. C.
Argonne National Laboratory. Metallurgy Division.
Language(s): English
Published: Lemont, Ill. : Argonne National Laboratory, 1960.
Subjects: Uranium.
Nuclear fuels.
Nuclear fuel rods > Nuclear fuel rods / Testing.
Nuclear reactors > Nuclear reactors / Materials.
Nuclear reactors > Nuclear reactors / Design and construction.
Nuclear fuel elements > Nuclear fuel elements / Design and construction.
Note: "Portions of the material contained in this report appeared in the following Metallurgy Division Progress Reports: ANL-5837 ... ; ANL-5975 ... "
"Final Report -- Metallurgy Program 7.6.9"
"AEC Research and Development Report"
"(TID-4500, 15th Ed.)"
"Metallurgy and Ceramics"
Physical Description: 26 p. : ill. ; 28 cm.
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