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
·
OSTI ID:7213720
A study of hydrogen pickup by oxidized Zircaloy specimens was made. The results of hydrogen analyses are presented, and the mechanism by which hydrogen enters the specimens is discussed. Data obtained at 900/sup 0/C (1652/sup 0/F) in steam at 3.45 MPa (500 psi) suggest that steam pressure does not have a significant effect on the oxidation rate of Zircaloy; partially complete data at 1100/sup 0/C (2012/sup 0/F) also appear to support this conclusion.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7213720
- Report Number(s):
- ORNL/NUREG/TM-110
- Country of Publication:
- United States
- Language:
- English
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Tue Jul 26 00:00:00 EDT 1977
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·
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·
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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
·
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·
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
ABSORPTION
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CRYOGENIC FLUIDS
ELEMENTS
FLUIDS
FUEL-COOLANT INTERACTIONS
HYDROGEN
HYDROGEN COMPOUNDS
LOSS OF COOLANT
NONMETALS
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
ABSORPTION
ACCIDENTS
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CRYOGENIC FLUIDS
ELEMENTS
FLUIDS
FUEL-COOLANT INTERACTIONS
HYDROGEN
HYDROGEN COMPOUNDS
LOSS OF COOLANT
NONMETALS
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