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'eau

Additional 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).