Published March 2, 1973
| Version v1
Patent
Zirconium alloys
Description
A method is described for the preparation of nuclear reactor components such as fuel cans and pressure-tubes in zirconium alloys. The method is characterized in that use is made of zirconium alloys with from 0.16 to 0.25% oxygen, by weight, and in that these elements are submitted to an annealing operation, at a temperatures of from 400 to 750 deg C. The thus obtained structural elements are used in water cooled nuclear reactor
Abstract (French)
On decrit un procede d'elaboration d'elements de reacteurs nucleaires tels que des gaines et des tubes de force en alliage de zirconium. Le procede est caracterise par le fait que l'on utilise des alliages de zirconium ayant une teneur de 0,16 a 0,25% en poids d'oxygene et que l'on soumet lesdits elements a un recuit a une temperature comprise entre 400 et 750 deg C. Les elements de structures obtenues sont utilises dans des reacteurs nucleaires refroidis a l'eauAdditional details
Additional titles
- Original title (French)
- Alliages de zirconium
- Augmented title (English)
- reactor components
Publishing Information
- Imprint Pagination
- 6 p.
- IPC:
- Int. Cl. C22c15/00; C22f1/16; G21c3/06; G21c21/00.
- IPC
- Int. Cl. C22c15/00; C22f1/16; G21c3/06; G21c21/00.
- Patent number
- FR patent document 2219978/A/
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 6218622
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- CREEP; ELASTICITY; FABRICATION; FUEL CANS; PRESSURE TUBES; REACTOR COMPONENTS; ZIRCALOY 4
- Descriptors DEC
- ALLOYS; MECHANICAL PROPERTIES; TENSILE PROPERTIES; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; TUBES; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Notes
- Available from Institut National de la Propriete Industrielle, Paris (France).