An empirical prediction of temperature gradients in moderator graphite within operating nuclear reactors /
by Robert L. Carter.

Description

Main Author

Carter, Robert L.

Related Names

North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

Language(s)

English

Published

Canoga Park, California : Atomics International, [1962]

Subjects

Sodium graphite reactors.
Graphite > Graphite / Thermal properties.
Sodium graphite reactors.
Graphite > Graphite / Thermal properties.

Note

"NAA-SR-6616 ; Reactor technology."
"Contract AT(11-1)-GEN-8 ; Issued: Feb 15 1962."

Physical Description

vi, 44 pages : illustrations ; 28 cm.

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