FRAPCON-2 :
a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods /
prepared by G.A. Berna ... [and others] ; prepared for Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.

Description

Related Names

Berna, Gary A.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Pacific Northwest Laboratory.
EG & G Idaho.

Language(s)

English

Published

Washington, D.C. : The Commission : 1981.

Subjects

Nuclear fuel claddings > Nuclear fuel claddings / Data processing.
Nuclear fuel rods > Nuclear fuel rods / Data processing.
Oxidation.

Note

"NUREG/CR-1845."
"NRC FIN no. A6050, B2043."
"Date published: January 1981."
"Pacific Northwest Laboratory."
"EG&G Idaho, Inc."

Physical Description

x, 282 p. : ill. ; 28 cm

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