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88篇 您的检索式：作者名="ODETTE R G"

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	题名	作者	年代	出处	被引量
1	The development and stability of Y-Ti-O nanoclusters in mechanically alloyed Fe-Cr based ferritic alloys 显示文摘	ALINGER M J ODETTE G R HOELZER D T J	2004	J Nucl Mater2004，，1：	1
2	Recent progress in understandingreactor pressure vessel steel embrittlement显示文摘	Odette G R Lucas G E	1998	Radiat Eft Defects Solids1998，114，：	1
3	Some recent innovations in small specimen testing 显示文摘	Odette G R He M Gragg D Klingensmith D Lucas G E	2002	Journal of Nuclear Materials2002，，：	1
4	TEM examination of microstructural evolution during processing of 14CrYWTi nanostructured ferritie alloys 显示文摘	KISHMOTO H ALINGER M J ODETTE G R	2004	Journal of Nuclear Materials2004，，1：	1
5	On the Role of Alloy Composition and Processing Parameters in Nnanocluster Formation and Dispersion Strengthening in Nanostuctured Ferritic Alloys 显示文摘	Alinger M J Odette G R Hoeher D T	2009	Acta Materialia2009，57，：	1
6	A master curve analysis of F82H using statistical and constraint loss size adjustments of small specimen data显示文摘	Odette G R Yamamoto Y Kishimoto H	2004	Jour- nal of Nuclear Materials2004，329，：	1
7	The transport and fate of helium in nanostructured ferritic alloys at fusion relevant He/ dpa ratios and dpa rates显示文摘	YAMAMOTO T ODETTE G R MIAO P	2007	J Nucl Mater2007，，：	1
8	On the effects of irradiation on the yield stress changes and hardening and non - hardening embrittlement of 8Cr tempered martensitic steels: compilation and analysis of existing data 显示文摘	Yamamoto T Odette G R Kishimoto H	2006	J Nucl Mater2006，356，：	1
9	Micromechanical modeling of mas- ter curve temperature shifts due to constraint loss 显示文摘	Odette G R He M Y	2002	Journal of Nuclear Materials2002，7，：	1
10	On the Dominant Mechanism of Irradiation Embrittlement of Reactor Pressure Vessel Steels显示文摘	ODETTE G R		0，，10：	1
11	The development and stability of Y-Ti-O nano-clusters in mechanically alloyed Fe-Cr based ferritic alloys显示文摘	ALINGER M J ODETTE G R HOEZER D T	2004	J Nucl Mater2004，，：	1
12	Recent de- velopments in irradiation resistant steels显示文摘	ODETTE G R ALINGER M J WIRTH B D	2008	Annual Review of Materials Research2008，38，：	1
13	Embrittlement of nuclear reactor pressure vessels显示文摘	Odette G R Lucas G E	2001	JOM2001，53，7：	1
14	Hardening and microstructure evolution in proton-irradiated model and commercial pressure-vessel steels 显示文摘	Was G S Hash M Odette R G	2005	Philosophical Magazine2005，85，47：	1
15	On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostructured ferritic alloys显示文摘	ALINGER M J ODETTE G R HOELZER D T	2009	Acta Materialia2009，57，：	1
16	Precipitation in neu- tron-irradiated Fe-Cu and Fe-Cu-Mn model alloys: A com- parison of APT and SANS data显示文摘	Miller M K Wirth B D Odette G R	2003	Mater Sci Eng A2003，353，12：	1
17	查看详情显示文摘	ODETTE G R		0，，：	1
18	The development and stability of Y-Ti-O nanoclusters in mechanically alloyed Fe-Cr based ferritic alloys 显示文摘	ALINGER M J ODETTE G R HOELZER D T	2004	Journal of Nuclear Materials2004，，：	1
19	Some recent innovations in small specimen testing显示文摘	ODETTE G R HE M GRAGG D	2002	Journal of Nuclear Materials2002，，02：	1
20	查看详情显示文摘	ODETTE G R		0，，：	1

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