Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor :
materials tests 1 and 2 /
prepared by G.E. Russcher ... [et al.]

Description

Related Names

Russcher, G. E.
Pacific Northwest Laboratory.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

Language(s)

English

Published

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

Subjects

Nuclear fuel claddings > Nuclear fuel claddings / Materials > Nuclear fuel claddings / Materials / Testing.
Pressurized water reactors > Pressurized water reactors / Loss of coolant.
Nuclear reactor accidents > Nuclear reactor accidents / Simulation methods.

Note

"PNL-3765."
"NUREG/CR-1735, Addendum 1."
"NRC FIN B2277."
"Date published: September 1981."
"Pacific Northwest Laboratory."

Physical Description

37 p. in various pagings : ill. ; 28 cm.

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