Published July 7, 1994 | Version v1
Patent Metadata-only

Manufacture of materials and workpieces having fine grain for components in nuclear plant applications

Creators

Description

Austenitic steel for components intended to be used in radiation zones of nuclear reactors is largely resistant to irradiation-induced stress corrosion if its silicon, phosphorus and sulfur content is reduced in relation to standard commercial steel quantities and its grain structure has an average grain diameter under approximately 20 μm. The optimum grain structure is achieved when annealing is avoided at temperatures over 950 oC. When niobium is added as a carbide former leading to a fine dispersion of carbides, and increased resistance to irradiation induced stress corrosion cracking is still achievable when annealing temperatures under approximately 1075 oC are used. (author)

Availability note (English)

Available from WIPO, 34, chemin des Colombettes, CH-1211 Geneva (CH).

Additional details

Publishing Information

Imprint Pagination
34 p.
IPC:
Int. Cl. C22C 38/48; C21D 8/00.
IPC
Int. Cl. C22C 38/48; C21D 8/00.
Patent number
WO patent document 9414992/A1/

INIS

Country of Publication
Switzerland
Country of Input or Organization
Switzerland
INIS RN
26000318
Subject category
S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Numerical Data, Non-conventional Literature
Descriptors DEI
ANNEALING; AUSTENITIC STEELS; CARBIDES; FABRICATION; GRAIN SIZE; NIOBIUM; NUMERICAL DATA; PHOSPHORUS; PHYSICAL RADIATION EFFECTS; REACTORS; SILICON; STRESS CORROSION; SULFUR; TEMPERATURE RANGE 1000-4000 K
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CARBON COMPOUNDS; CHEMICAL REACTIONS; CORROSION; CRYSTAL STRUCTURE; DATA; ELEMENTS; HEAT TREATMENTS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; METALS; MICROSTRUCTURE; NONMETALS; RADIATION EFFECTS; SEMIMETALS; SIZE; STEELS; TEMPERATURE RANGE; TRANSITION ELEMENTS

Optional Information

Secondary number(s)
US patent application 9211260.