Precipitation hardening type single crystal austenitic steel, and usage the same
US5987088A · kind A · utility
Assignee
Inventors
Key dates
| Filing date | Apr 21, 1998 |
| Grant date | Nov 16, 1999 |
| Priority date | — |
| Expiry date | Apr 21, 2018 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY10S376/90
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
In order to provide an austenitic single crystal stainless steel having preferable stress corrosion cracking resistance, strength, and irradiation induced embrittlement resistance so as to extend the life of a nuclear reactor core structure, which is used under a high radiation dose environment, a method is employed, which comprises the steps of homogeneously dispersing carbides into a parent phase of the austenitic single crystal stainless steel by a two step solution heat treatment, and subsequently effecting an ageing heat treatment after rapid cooling for precipitating fine carbides. Austenitic single crystal stainless steel having preferable stress corrosion cracking resistance, strength, and irradiation induced embrittlement resistance can be provided, and the life of nuclear reactor core structure, which is used under a high radiation dose environment, can be extended.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.