Zirconium metal-water oxidation kinetics. V. Oxidation of Zircaloy in high pressure steam. [PWR]

Technical Report · Thu Dec 01 00:00:00 EST 1977

DOI:https://doi.org/10.2172/5273792· OSTI ID:5273792

Pawel, R E; Cathcart, J V; Campbell, J J; Jury, S H

A series of scoping tests to determine the influence of steam pressure on the isothermal oxidation kinetics of Zircaloy-4 PWR tubing was undertaken. The oxidation experiments were conducted in flowing steam at 3.45, 6.90, and 10.34 MPa (500, 1000, and 1500 psi) at 905/sup 0/C (1661/sup 0/F), and at 3.45 and 6.90 MPa at 1101/sup 0/C (2014/sup 0/F). A comparison of the results of these experiments with those obtained for oxidation in steam at atmospheric pressure under similar conditions indicated that measurable enhancement of the oxidation rate occurred with increasing pressure at 905/sup 0/C, but not at 1100/sup 0/C.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5273792
• Report Number(s): ORNL/NUREG-31; TRN: 78-002596
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
FUEL CANS
OXIDATION
PWR TYPE REACTORS
ZIRCALOY 4
CHEMICAL REACTION KINETICS
DATA
HIGH PRESSURE
PRESSURE DEPENDENCE
STEAM
TEMPERATURE DEPENDENCE
VERY HIGH TEMPERATURE
ALLOYS
CHEMICAL REACTIONS
INFORMATION
KINETICS
REACTION KINETICS
REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360105 - Metals & Alloys- Corrosion & Erosion