Quarterly progress report on the zirconium metal-water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research, April--June 1976. [LWR's]
Technical Report
·
OSTI ID:7338208
Except for scoping tests of the influence of steam pressure on the oxidation behavior of Zircaloy-4, the experimental phase of the reaction rate studies was completed. Kinetic data for the isothermal steam-Zircaloy reaction between 900 and 1500/sup 0/C (1652--2732/sup 0/F) are reported, and the parabolic rate constants for the growth of oxide, alpha, and Xi (oxide + alpha) layers as well as that for total oxygen consumption are given in the form of Arrhenius equations. The transient temperature oxidation experiments are described along with scoping tests of the effects of steam impurities and small variations in alloy content. A study of the oxidation of Zircaloy in high pressure steam was initiated, and a final report on our investigation of the diffusion of oxygen in ..beta..-Zircaloy-4 was prepared. The results of a limited number of oxygen diffusivity measurements in oxygen-stabilized ..cap alpha..-Zircaloy-4 are also reported.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7338208
- Report Number(s):
- ORNL/NUREG/TM-41
- Country of Publication:
- United States
- Language:
- English
Similar Records
Zirconium metal--water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research. Quarterly progress report, January--March 1976. [BWR; PWR]
Quarterly progress report on the zirconium metal-water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research for October--December 1975
Diffusion of oxygen in beta-Zircaloy and the high temperature Zircaloy-steam reaction
Technical Report
·
Sat May 01 00:00:00 EDT 1976
·
OSTI ID:7274426
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
·
Sun Feb 29 23:00:00 EST 1976
·
OSTI ID:4003322
Diffusion of oxygen in beta-Zircaloy and the high temperature Zircaloy-steam reaction
Journal Article
·
Fri Dec 31 23:00:00 EST 1976
· Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
·
OSTI ID:6663408
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
FUEL-COOLANT INTERACTIONS
HYDROGEN COMPOUNDS
IRON ADDITIONS
IRON ALLOYS
LOSS OF COOLANT
OXIDATION
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH PROGRAMS
STEAM
TIN ALLOYS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 2
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ADDITIONS
CHROMIUM ALLOYS
FUEL-COOLANT INTERACTIONS
HYDROGEN COMPOUNDS
IRON ADDITIONS
IRON ALLOYS
LOSS OF COOLANT
OXIDATION
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
RESEARCH PROGRAMS
STEAM
TIN ALLOYS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 2
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS