Published February 1983
| Version v1
Journal article
Corrosion of zirconium alloys in power reactor superheated steam
Description
The results of investigation into kinetics of zirconium alloy corrosion in power reactor channel superheated steam by means of the resistometric method are presented. It is revealed that the rate of Zr+2.5% Nb alloy corrosion under neutron flux irradiation with 3.8x1013 neutr./(cm2xs) intensity at E>=0.8 MeV decreases and the Zr+1% Fe+1% Cr+0.4% W alloy stronger corrode under the same conditions. The results agree with data obtained by the weight method
Additional details
Additional titles
- Original title (Russian)
- Коррозия циркониевых сплавов в перегретом паре энергетического реактора
Publishing Information
- Journal Title
- At. Ehnerg.
- Journal Volume
- 54
- Journal Issue
- 2
- Series
- At. Ehnerg.
- Journal Page Range
- 114-116
- ISSN
- 0004-7163
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- USSR
- INIS RN
- 14805471
- Subject category
- S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Descriptors DEI
- CHEMICAL COMPOSITION; CHEMICAL REACTION KINETICS; CORROSION; FLUX DENSITY; NEUTRON FLUX; POWER REACTORS; STEAM; SUPERHEATING; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; HEATING; KINETICS; RADIATION FLUX; REACTION KINETICS; REACTORS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS
Optional Information
- Notes
- For English translation see the journal Soviet Journal of Atomic Energy (USA).