Process for eliminating deposits formed in a steam generator of a pressurized water nuclear reactor
US4686067A · kind A · utility
15Cited by
6References
6Claims
0Family size
Assignee
Inventors
Key dates
| Filing date | Dec 28, 1984 |
| Grant date | Aug 11, 1987 |
| Priority date | — |
| Expiry date | Dec 28, 2004 |
Classification
- Technology area (CPC G)Physics
- CPC primaryG21F9/004
- WIPO fieldEngines, pumps, turbines
- WIPO sectorMechanical engineering
Abstract
Process for the elimination of corrosion products formed on the tube plate and in the gaps between the tubes and the spacer plates of a steam generator of a pressurized water nuclear reactor, in order to prevent the appearance of a corrosion phenomena, which can lead to necking or denting of tubes by oxide growth. The process consists of reacting with said oxides at between 50.degree. and 100.degree. C., an aqueous solution containing 6 to 8% gluconic acid, 3 to 5% citric acid, approximately 0.5% of a corrosion inhibitor and ammonia until a pH between approximately 3 and 9.5 is obtained.
Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.