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Ghoniem, N.; Zinkle, S.
Joint EC-IAEA topical meeting on development of new structural materials for advanced fission and fusion reactor systems. PowerPoint presentations2009
Joint EC-IAEA topical meeting on development of new structural materials for advanced fission and fusion reactor systems. PowerPoint presentations2009
AbstractAbstract
[en] Significant progress has been achieved in the operational performance and radiation resistance of ferritic-martensitic steels during the past few decades. Conventional high temperature steels, such as HT-9 and 2 1/4 Cr-1Mo have evolved into super Oxide Dispersion Strengthened (ODS) steels through successive optimization to meet strict performance and radiation-resistance constraints. Such evolution was possible through a combination of experimentation, modeling and empirical information. Further development and optimization of structural steels in nuclear applications will require full utilization of the available array of sophisticated experimental techniques and multiscale computational modeling, in addition to empirical data. We present here a systematic approach to the process of optimum steel development, by linking material fabrication to thermo-mechanical properties through a physical understanding of microstructure evolution. The optimization process is based on the application of design constraints (e.g. low activation, low DBTT, low swelling, creep resistance, and weldability) to describe the required microstructures, which in turn, can be controlled through material processing techniques. Prospects for future design of optimum structural steels in nuclear applications by utilization of the hierarchy of multiscale experimental and computational strategies will be described. (author)
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European Commission, Joint Research Centre, Institute for Energy, Petten (Netherlands); International Atomic Energy Agency, Division of Physical and Chemical Sciences, Physics Section, Vienna (Austria); Fusion for Energy, Barcelona (Spain); European Nuclear Society, Brussels (Belgium); vp; 2009; [36 p.]; Joint EC-IAEA topical meeting on development of new structural materials for advanced fission and fusion reactor systems; Barcelona (Spain); 5-9 Oct 2009; Published as PowerPoint presentation only
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ATOMIC DISPLACEMENTS, AUSTENITIC STEELS, CREEP, DEFORMATION, DUCTILE-BRITTLE TRANSITIONS, EMBRITTLEMENT, IRRADIATION, MICROSTRUCTURE, PHASE STABILITY, PWR TYPE REACTORS, REACTOR MATERIALS, REACTOR SHUTDOWN, REACTOR START-UP, SIMULATION, THERMONUCLEAR REACTOR MATERIALS, THERMONUCLEAR REACTORS, WELDABILITY
ALLOYS, CARBON ADDITIONS, ENRICHED URANIUM REACTORS, IRON ALLOYS, IRON BASE ALLOYS, MATERIALS, MECHANICAL PROPERTIES, PHYSICAL RADIATION EFFECTS, POWER REACTORS, RADIATION EFFECTS, REACTORS, SHUTDOWN, STABILITY, START-UP, STEELS, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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