000148225 001__ 148225
000148225 005__ 20190812205411.0
000148225 0247_ $$2doi$$a10.1016/j.jnucmat.2008.12.323
000148225 02470 $$2ISI$$a000266386900103
000148225 037__ $$aCONF
000148225 245__ $$aRecent progress toward development of reduced activation ferritic/martensitic steels for fusion applications
000148225 269__ $$a2009
000148225 260__ $$bElsevier$$c2009$$aThe Netherlands
000148225 336__ $$aConference Papers
000148225 520__ $$aSignificant progress has been achieved in the international research effort on reduced activation ferritic/martensitic steels for fusion structural applications. Because this class of steels is the leading structural material for test blankets in ITER and future fusion power systems, the range of ongoing research activities is extremely broad. Since, it is not possible to discuss all relevant work in this brief review, the objective of this paper is to highlight significant issues that have received recent attention. These include: (1) efforts to measure and understand radiation-induced hardening and embrittlement at temperatures <400 °C, (2) experiments and modeling to characterize the effects of He on microstructural evolution and mechanical properties, (3) exploration of approaches for increasing the high-temperature (>550 °C) creep resistance by introduction of a high-density of nanometer scale dispersoids or precipitates in the microstructure, (4) progress toward structural design criteria to account for loading conditions involving both creep and fatigue, and (5) development of nondestructive examination methods for flaw detection and evaluation.
000148225 6531_ $$aFatigue-Oxidation Interactions
000148225 6531_ $$aContaining Martensitic Steels
000148225 6531_ $$aMechanical-Properties
000148225 6531_ $$aHolding Period
000148225 6531_ $$aVacuum Vessel
000148225 6531_ $$aHelium
000148225 6531_ $$aIrradiation
000148225 6531_ $$aCreep
000148225 6531_ $$aComponents
000148225 6531_ $$aIter
000148225 700__ $$aKurtz, R. J.
000148225 700__ $$aAlamo, A.
000148225 700__ $$aLucon, E.
000148225 700__ $$aHuang, Q.
000148225 700__ $$aJitsukawa, S.
000148225 700__ $$aKimura, A.
000148225 700__ $$aKlueh, R. L.
000148225 700__ $$aOdette, G. R.
000148225 700__ $$aPetersen, C.
000148225 700__ $$aSokolov, M. A.
000148225 700__ $$0240522$$g106982$$aSpätig, P.
000148225 700__ $$aRensman, J. W.
000148225 7112_ $$dDecember 10-14, 2007$$cNice, France$$a13th International Conference on Fusion Reactor Materials
000148225 773__ $$j386-388$$tJournal of Nuclear Materials, Proceedings of the 13th International Conference on Fusion Reactor Materials$$q411-417
000148225 909C0 $$pCRPP
000148225 909C0 $$pSPC$$0252028$$xU10136$$xU12267$$xU12269$$xU12271$$xU10559$$xU12273$$xU10557$$xU12270$$xU10137$$xU10636$$xU12266$$xU10635$$xU10558$$xU12268$$xU12272
000148225 909CO $$pconf$$pSB$$ooai:infoscience.tind.io:148225
000148225 937__ $$aEPFL-CONF-148225
000148225 973__ $$rREVIEWED$$sPUBLISHED$$aEPFL
000148225 980__ $$aCONF