Materials Performance In Nuclear Pressurized Water Reactor Steam Generators
| Autor: | J. Peter N. Paine, Stanley J. Green |
|---|---|
| Rok vydání: | 1981 |
| Předmět: |
Nuclear and High Energy Physics
Materials science 020209 energy Metallurgy Pressurized water reactor Boiler (power generation) Fretting 02 engineering and technology Intergranular corrosion Condensed Matter Physics law.invention Corrosion 020303 mechanical engineering & transports 0203 mechanical engineering Nuclear Energy and Engineering law 0202 electrical engineering electronic engineering information engineering Stress corrosion cracking Inconel Nuclear chemistry Incoloy |
| Zdroj: | Nuclear Technology. 55:10-29 |
| ISSN: | 1943-7471 0029-5450 |
| DOI: | 10.13182/nt81-a32828 |
| Popis: | The nuclear industry has had a variety of reliability problems with pressurized water reactor steam generators. Most of these problems have been associated with corrosion and mechanically induced damage, including secondary water intergranular corrosion and stress corrosion cracking (SCC), primary water SCC, wastage, high cycle fatigue, and fretting and wear of the Inconel 600 or Incoloy 800 tubes, plus accelerated corrosion of carbon steel tube support structures in crevice regions. This article discusses steam generator material performance. 23 refs. |
| Databáze: | OpenAIRE |
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