Zirconium metal--water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research. Quarterly progress report, January--March 1976. [BWR; PWR]
Technical Report
·
OSTI ID:7274426
The correlation of data for the diffusion of oxygen in ..beta..-Zircaloy-4 between 900 and 1500/sup 0/C (1652-2732/sup 0/F) was completed. An error analysis of the diffusion techniques used was also made. The experimental phase of the isothermal oxidation measurements was completed, and the specimens are currently undergoing metallographic examination. Several improvements were made in the data acquisition procedures in order to determine accurately the time-temperature record for oxidation specimens, in short, high temperature experiments. Methods were devised for calculating from oxidation data the diffusion coefficients of oxygen in the oxide and ..cap alpha..-Zircaloy, and these values will be used along with new data for the equilibrium phase solubility limits for oxygen in the ..cap alpha.. and ..beta.. phases in the verification of the computer code.
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7274426
- Report Number(s):
- ORNL/NUREG/TM-17
- Country of Publication:
- United States
- Language:
- English
Similar Records
Quarterly progress report on the zirconium metal-water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research for October--December 1975
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]
Zirconium metal-water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research. Quarterly progress report, January--March 1977. [BWR; PWR]
Technical Report
·
Sun Feb 29 23:00:00 EST 1976
·
OSTI ID:4003322
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
·
Sun Aug 01 00:00:00 EDT 1976
·
OSTI ID:7338208
Zirconium metal-water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research. Quarterly progress report, January--March 1977. [BWR; PWR]
Technical Report
·
Thu Apr 28 00:00:00 EDT 1977
·
OSTI ID:7213720
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
DATA
FUEL-COOLANT INTERACTIONS
HYDROGEN COMPOUNDS
INFORMATION
IRON ADDITIONS
IRON ALLOYS
LOSS OF COOLANT
OXIDATION
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
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
DATA
FUEL-COOLANT INTERACTIONS
HYDROGEN COMPOUNDS
INFORMATION
IRON ADDITIONS
IRON ALLOYS
LOSS OF COOLANT
OXIDATION
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
SAFETY
STEAM
TIN ALLOYS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 2
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS