Influence of thermal processing and microstructure on the corrosion behaviour of Zircaloy-4 tubing
- 1. Sandvik Steel AB, Sandviken (Sweden). Research and Development Centre
Description
To minimize the corrosion, and hence the fuel cycle costs, of Zr-4 cladding, optimization of thermal processing and microstructure of the tubing is a necessity. This investigation was carried out in order to correlate the effect of thermal processing and microstructure of Zr-4 tubing with the 400 deg. C steam corrosion behaviour in a refreshed autoclave. To achieve this a number of different intermediate annealing treatments were performed on various specimens. It was found that shorter-lower temperature heat treatments at the intermediate annealing stage resulted in poor corrosion resistance when compared with longer-higher temperature treatments. A critical heat treatment existed which had to be exceeded to obtain good corrosion behaviour. For the given composition there was a saturation value of the corrosion behaviour, i.e. a minimum weight gain which was always obtained. The corrosion behaviour was modelled to the annealing parameter A=t exp (-Q/RT), which can be interpreted as a normalized annealing time. The factor governing the corrosion appeared to be the matrix solute content rather than the intermetallic particle size. The activation energy determined from the model, Q=63,000 cal/mol, did not correspond to any simple self-solute diffusion process. (author)
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna (Austria)
- ISBN
- 92-0-050087-0
- Imprint Title
- Improvements in water reactor fuel technology and utilization
- Imprint Pagination
- 621 p.
- Series
- Proceedings series.
- Journal Page Range
- p. 435-449.
Conference
- Title
- International symposium on improvements in water reactor fuel technology and utilization.
- Dates
- 15-19 Sep 1986.
- Place
- Stockholm (Sweden).
INIS
- Country of Publication
- Austria
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 18083172
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY-ZR98SN-4; ANNEALING; CORROSION; CORROSION RESISTANCE; FUEL CANS; HEAT TREATMENTS; HIGH TEMPERATURE; METALLOGRAPHY; PWR TYPE REACTORS; TESTING; THERMODYNAMICS
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTING ALLOYS; IRON ADDITIONS; POWER REACTORS; REACTORS; THERMAL REACTORS; TIN ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- 12 refs, 9 figs, 4 tabs.
- Secondary number(s)
- IAEA-SM--288/59.