Home > Publications database > Fracture mechanics and mechanical testing laboratory at Inshas report no. 2 |
Book | FZJ-2021-02223 |
; ; ;
1995
Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag
Jülich
ISBN: 3-89336-153-7
Please use a persistent id in citations: http://hdl.handle.net/2128/28531
Abstract: The steels used for the construction of nuclear reactor pressure vessels are low alloy ferritic steels. These steels must have good impact properties, i.e., low transition temperature and high upper shelf energy, both before and during being sublect to service conditions; the most important is neutron irradiation. Extensive R&D work has been conducted to make the production of such steels possible. In the present study instrumented impact testing was conducted for three advanced pressure vessel steels in comparison with a conventional pressure vessel steel. The first one of the advanced steels was a 20MnMoNi55 (ASTM A533-B C1.2) weld produced in Germany (GW). The second was an ASTM A508 CI.3 forging produced in France (FF). The third was an ASTM A533-B CI.1 plate produced in Japan (JP). The conventional steel was an ASTM A533-B CI.1 plate (HSST 03 plate) produced in USA (HSST) and it represents steels used in most nuclear reactor pressure vessels currently in operation. Both microstructure and fracture surface were examined using optical and SEM techniques. In general, the advanced steels showed much better impact properties (lower ductile-brittle transition temperature and higher upper shelf energy) than the conventional steel. The ductile-brittle transition temperature (DBTI) at 41 J(T41J) was -73, -57 and -44·C for the GW, FF and JP steels, respectively, [...]
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