Viscosity of zirconium-uranium oxide (Zr-UO.

Bibliographic Details
Main Author: Bunnell, L. R., 1943-
Corporate Authors: U.S. Nuclear Regulatory Commission. Division of Reactor System Safety
Pacific Northwest Laboratory
Other Authors: Prater, J. T.
Language:English
Published: Washington, DC : Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986.
Subjects:
Viscosity.
Zirconium oxide.
Uranium.
Pressurized water reactors > Loss of coolant.
Physical Description:x, 35, 3 pages : illustrations ; 28 cm
Format: Government Document Book
Description
Note:"Pacific Northwest Laboratory."
Distributed to depository libraries in microfiche.
"Date published: September 1986."
Microform.
Call Number:Y 3.N 88:25/4495
Bibliography Note:Bibliography: page 29.
Type of Report and Period Covered:
Technical.