Ferritic/martensitic dual-phase steel as fusion reactor materials
Description
In ferritic/martensitic steels, the swelling rate is much lower than in austenitic steels. Therefore, ferritic/martensitic steels may become the next candidate alloys for the first wall of future fusion reactors. Until now, the martensitic steels HT-9 and modified 9Cr-1Mo steel have been investigated. These steels have excellent high-temperature creep properties but are not necessarily better in Ductile Brittle Transition Temperature (DBTT) properties than austenitic steel. Especially their weldability is a problem. For these reasons new ferritic/martensitic dual-phase steels have been considered. In this presentation, the advantages and disadvantages in their use as fusion reactor materials will be discussed. The recommended compositions are mainly low-C 9Cr-1 or 2Mo including some modifications. Since these alloys have wider two-phase regions than 9Cr-1Mo steel, after normalizing, a ferritic/martensitic structure with a fixed percentage of ferrite can be obtained. The mechanical properties, weldability and other properties are compared between single- and dual-phase steels. And the characteristics of the ferritic/martensitic dual phase steels are introduced. (orig.)
Additional details
Publishing Information
- Journal Title
- J. Nucl. Mater.
- Journal Volume
- 133/134
- Series
- J. Nucl. Mater.
- Journal Page Range
- 141-148
- ISSN
- 0022-3115
- CODEN
- JNUMA
Conference
- Title
- 1. international conference on fusion reactor materials (ICFRM-1).
- Dates
- 3-6 Dec 1984.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 17015975
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CHARPY TEST; CRACKING; CREEP; DUCTILE-BRITTLE TRANSITIONS; EMBRITTLEMENT; EXPERIMENTAL DATA; FATIGUE; FERRITIC STEELS; FIRST WALL; HARDNESS; HIGH TEMPERATURE; HYDROGEN ADDITIONS; MARTENSITIC STEELS; MICROSTRUCTURE; PHASE DIAGRAMS; RADIATION EFFECTS; STEEL-CR12MOV; STEEL-CR9MO; TENSILE PROPERTIES; THERMONUCLEAR REACTOR MATERIAL; TRANSMISSION ELECTRON MICROSCO; WELDABILITY
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DATA; DECOMPOSITION; DESTRUCTIVE TESTING; DIAGRAMS; ELECTRON MICROSCOPY; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IMPACT TESTS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MATERIALS TESTING; MECHANICAL PROPERTIES; MECHANICAL TESTS; MICROSCOPY; MOLYBDENUM ADDITIONS; NUMERICAL DATA; PYROLYSIS; STAINLESS STEELS; STEELS; TESTING; THERMONUCLEAR REACTOR WALLS; VANADIUM ADDITIONS