Properties of reactor fuel rod materials at high temperatures
Subtitle: final summary report : severe core damage property tests program
By: prepared by J.T. Prater, E.L. Courtright.
Contributors: Courtright, E. L.; U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor Accident Analysis.; Pacific Northwest Laboratory.
Publisher: Division of Reactor Accident Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Published: 1987
Place of publication: Washington, DC
Language: eng
Number of pages: 33
Subjects: Nuclear fuel rods -- Thermal properties.; Zirconium alloys.; Oxidation.
Notes: "Pacific Northwest Laboratory."

Distributed to depository libraries in microfiche.

"Date published: July 1987."

Bibliography: p. 31-33.

Technical.

B2455.