Corrosion Properties of Zircaloy-4 and M5 under Simulated PWR Water Conditions
| Autor: | Masatoshi Futakawa, Yoshiaki Kato, Katsuhiro Maekawa, Taketoshi Taguchi, Akira Shibata |
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| Rok vydání: | 2016 |
| Předmět: |
Cladding (metalworking)
Nuclear and High Energy Physics Materials science Nuclear fuel Metallurgy Zirconium alloy Pressurized water reactor 02 engineering and technology 021001 nanoscience & nanotechnology Condensed Matter Physics Corrosion law.invention 020303 mechanical engineering & transports 0203 mechanical engineering Nuclear Energy and Engineering law 0210 nano-technology |
| Zdroj: | Nuclear Technology. 196:89-99 |
| ISSN: | 1943-7471 0029-5450 |
| DOI: | 10.13182/nt16-54 |
| Popis: | Zircaloy-4 has been widely used as a nuclear fuel cladding material. However, recently, several European countries have gradually replaced Zircaloy-4 cladding material in pressurized water reactor ... |
| Databáze: | OpenAIRE |
| Externí odkaz: |
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