Viscosity of zirconium-uranium oxide (Zr-UO₂) mixtures at 1800 to 2100C̊
By: L.R. Bunnell, J.T. Prater.
Contributors: Prater, J. T.; U.S. Nuclear Regulatory Commission. Division of Reactor System Safety.; Pacific Northwest Laboratory.
Publisher: Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Published: 1986
Place of publication: Washington, DC
Language: eng
Number of pages: 35
Subjects: Viscosity.; Zirconium oxide.; Uranium.; Pressurized water reactors -- Loss of coolant.
Other titles: Viscosity of zirconium uranium oxide (Zr-UO₂) mixtures at 1800 to 2100C̊.
Notes: "Pacific Northwest Laboratory."

Distributed to depository libraries in microfiche.

"Date published: September 1986."

Bibliography: p. 29.

Technical.

B2455.