Quarterly progress report on the zirconium metal-water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research for October--December 1975

Technical Report · Mon Mar 01 04:00:00 EST 1976

OSTI ID:4003322

Cathcart, J V

The experimental phase of the study of the diffusivity of oxygen in $beta$-Zircaloy between 900 and 1500$sup 0$C (1652--2732$sup 0$F) is essentially complete. No differences between chemical and tracer diffusivities were observed, and between 1000 and 1500$sup 0$C (1832--2732$sup 0$F) the combined data set could be represented by D = 2.48 x 10$sup -2$ exp (-28200/RT) cm$sup 2$/ sec. The forty specimens (from a standard batch of Zircaloy tubing) required to define isothermal oxidation rate curves at 900, 1000, 1100, and 1300$sup 0$C (1652, 1832, 2012, and 2372$sup 0$F) have been oxidized in the MiniZWOK apparatus and are undergoing metallographic examination. Oxidation rate data obtained at 900 and 1000$sup 0$C (1652--1832$sup 0$F) in the MaxiZWOK apparatus are presented, and the procedures following in evaluating and correlating such data are described in detail.

• Research Organization: Oak Ridge National Lab., Tenn. (USA)
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-33-032385
• OSTI ID: 4003322
• Report Number(s): ORNL/TM--5248
• Country of Publication: United States
• Language: English

Related Subjects

*BWR TYPE REACTORS-- FUEL CANS
*FUEL CANS-- OXIDATION
*PWR TYPE REACTORS-- FUEL CANS
*ZIRCALOY 4-- OXIDATION
220900* --Nuclear Reactor Technology--Reactor Safety
LOSS OF COOLANT
N50210 --Metals
Ceramics
& Other Materials--Metals & Alloys--Corrosion & Erosion & Surface Phenomena
N77100 --Reactors--Power Reactors
Non-breeding
Light-water Moderated
Boiling Water-cooled
N77200 --Reactors--Power Reactors
Non-breeding
Light-water Moderated
Non-boiling Water-cooled
N77900* --Reactors--Reactor Safety & Environmental Aspects
REACTOR SAFETY
RESEARCH PROGRAMS
STEAM
WATER
ZIRCONIUM ALLOYS