Published September 1978
| Version v1
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Some observations of the corrosion of zircaloy-4 as compared with zircaloy-2 in reactor and autoclave environments
- 1. UKAEA, Springfields. Nuclear Power Development Labs.
Description
The corrosion behaviour of zircaloy-4 in autoclaves, in the X-6 loop of the Canadian NRX reactor, and in the Winfrith SGHWR is reported. The only significant difference between Zircaloy-4 and Zircaloy-2 were that the hydrogen uptake in autoclave tests was lower for Zircaloy-4, but Zircaloy-4 was rather more susceptible to loss of oxide by spalling in certain conditions, and on two occasions Zircaloy-4 suffered uniquely high corrosion rates. (author)
Availability note (English)
MF available from INIS under the Report Number; Also available from H.M. Stationery Office, price Pound1.50.
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The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- ISBN
- 0 85 356116 8
- Imprint Pagination
- 30 p.
- Report number
- ND-R--152(S)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 10429614
- Subject category
- S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Descriptors DEI
- AUTOCLAVES; COMPARATIVE EVALUATIONS; CORROSION; HIGH PRESSURE; HIGH TEMPERATURE; HYDROGEN; IN PILE LOOPS; RADIOLYSIS; STEAM; TRANSIENTS; WATER; WATER VAPOR; ZIRCALOY 2; ZIRCALOY 4
- Descriptors DEC
- ALLOYS; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; DECOMPOSITION; ELEMENTS; FLUIDS; GASES; HYDROGEN COMPOUNDS; IRON ADDITIONS; NONMETALS; OXYGEN COMPOUNDS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; VAPORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS