Published December 1977
| Version v1
Report
Open
Zirconium metal-water oxidation kinetics. V. Oxidation of Zircaloy in high pressure steam
Description
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 9050C (16610F), and at 3.45 and 6.90 MPa at 11010C (20140F). 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 9050C, but not at 11000C
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.Files
9374217.pdf
Files
(617.9 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:866b6dd23e0cc8834a5da79ad844fc60
|
617.9 kB | Preview Download |
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 29 p.
- Report number
- ORNL/NUREG--31
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9374217
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Descriptors DEI
- CHEMICAL REACTION KINETICS; DATA; FUEL CANS; HIGH PRESSURE; OXIDATION; PRESSURE DEPENDENCE; PWR TYPE REACTORS; STEAM; TEMPERATURE DEPENDENCE; VERY HIGH TEMPERATURE; ZIRCALOY 4
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; INFORMATION; KINETICS; REACTION KINETICS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS