Published June 10, 1980 | Version v1
Patent Metadata-only

Zirconium-base alloy nuclear fuel container and method

Creators

Description

The invention is concerned with a novel zirconium-base alloy for nuclear reactor fuel cladding having unique corrosion resistance, ductility and load-carrying capacity (resistance to stress corrosion) and possibly corrosion resistance in the irradiated condition. The improved properties are due to the addition of from 0.05 to 0.25 percent beryllium, heat treatment by quenching from 9000C, and subjecting the material to a year or more of boiling water reactor conditions. (LL)

Availability note (English)

Available from Micromedia Ltd., 165 Hotel de Ville, Hull, Quebec, Canada J8X 3X2.

Additional details

Publishing Information

Imprint Pagination
16 p.
IPC:
Int. Cl. C22c 16/00.
IPC
Int. Cl. C22c 16/00.
Patent number
CA patent document 1079093/A/

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
12605482
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
BERYLLIUM ADDITIONS; CORROSION RESISTANT ALLOYS; FUEL CANS; IODINE; QUENCHING; STRESS CORROSION; ZIRCONIUM BASE ALLOYS
Descriptors DEC
ALLOYS; CHEMICAL REACTIONS; CORROSION; ELEMENTS; HALOGENS; HEAT TREATMENTS; NONMETALS; TRANSITION ELEMENT ALLOYS; ZIRCONIUM ALLOYS