A nuclear reactor comprising a reactor vessel and structural members made of an austenitic stainless steel having superior resistance to irradiation-induced segregation
US5316597A · kind A · utility
Assignee
Inventors
Key dates
| Filing date | Aug 28, 1992 |
| Grant date | May 31, 1994 |
| Priority date | — |
| Expiry date | Aug 28, 2012 |
Classification
- Technology area (CPC Y)Emerging Cross-Sectional Technologies
- CPC primaryY10S376/90
- WIPO fieldMaterials, metallurgy
- WIPO sectorChemistry
Abstract
A nuclear reactor having structural members made of austenitic stainless steel which is corrosion-resistant in an environment of neutron irradiation, and can suppress stress corrosion cracking and embrittlement. At least one additive selected from the group consisting of Ti more than 0.2% by weight but not more than 0.6%, Zr more than 0.2% but not more than 1.14%, Hf more than 0.2% but not more than 2.24%, V more than 0.2% but not more than 0.64%, Nb more than 0.5% but not more than 1.17% and Ta more than 0.5% but not more than 2.27% is added to austenitic stainless steel containing Cr, Ni and so on, and said at least one exists in a solid-solution state. In addition, the steel has a wholly austenitic structure substantially free of carbide. In order to maintain the irradiation-induced segregation prevention effected by the addition element, the C content is limited to 0.01 to 0.008%, and the N content is limited to 0.001 to 0.0%. The irradiation-induced segregation, of the constituent elements, such as Cr and Ni, occurring in a grain boundary under irradiation, can be prevented, and the deterioration of the corrosion resistance of the material, as well as the embrittlement, can be…
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.