Quarterly progress report on the zirconium metal--water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research, April--June 1977. [BWR; PWR]
Technical Report
·
OSTI ID:7301884
Scoping tests of the effect of steam pressure on the oxidation rate of Zircaloy-4 yielded negative results at 1100/sup 0/C (2012/sup 0/F) for steam at 3.45 MPa (500 psi); problems with reproducibility were encountered at 900/sup 0/C (1652/sup 0/F). Additional experiments in 6.9 MPa (1000 psi) steam are in progress. Measurements of the oxidation rate of Zircaloy-4 specimens in pure oxygen led to the conclusion that hydrogen previously reported present in oxidized specimens had no effect on measured rates of oxidation in steam. Additional in situ tests in the MiniZWOK apparatus confirmed the validity of previous estimates of maximum temperature measurement uncertainties.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7301884
- Report Number(s):
- ORNL/NUREG/TM-132
- 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 1977. [BWR; PWR]
Quarterly progress report on the zirconium metal--water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research for July--September 1977. [PWR, BWR]
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
·
Thu Apr 28 00:00:00 EDT 1977
·
OSTI ID:7213720
Quarterly progress report on the zirconium metal--water oxidation kinetics program sponsored by the NRC Division of Reactor Safety Research for July--September 1977. [PWR, BWR]
Technical Report
·
Sun Oct 30 23:00:00 EST 1977
·
OSTI ID:5412863
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
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
DATA
FUEL-COOLANT INTERACTIONS
HYDROGEN COMPOUNDS
INFORMATION
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 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
DATA
FUEL-COOLANT INTERACTIONS
HYDROGEN COMPOUNDS
INFORMATION
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 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS