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3152篇 您的检索式：期刊名="Journal of Nuclear Materials"

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	题名	作者	年代	出处	被引量
1	Corrosion and stress corrosion cracking in supercritical water显示文摘	G.S. Was P. Ampornrat G. Gupta S. Teysseyre E.A. West T.R. Allen K. Sridharan L. Tan Y. Chen X. Ren C. Pister	2007	Journal of Nuclear Materials2007，，1：	5
2	Microstructural characterization of Y 2 O 3 ODS–Fe–Cr model alloys显示文摘	V. de Castro T. Leguey A. Mu?oz M.A. Monge R. Pareja E.A. Marquis S. Lozano-Perez M.L. Jenkins	2009	Journal of Nuclear Materials2009，，：	3
3	Glass–ceramic nuclear waste forms obtained from SiO 2 –Al 2 O 3 –CaO–ZrO 2 –TiO 2 glasses containing lanthanides (Ce, Nd, Eu, Gd, Yb) and actinides (Th): study of internal crystallization显示文摘	P. Loiseau D. Caurant N. Baffier L. Mazerolles C. Fillet	2004	Journal of Nuclear Materials2004，，1：	3
4	Microstructure and properties of a Cu–Cr–Zr alloy显示文摘	I.S. Batra G.K. Dey U.D. Kulkarni S. Banerjee	2001	Journal of Nuclear Materials2001，，2：	2
5	Glass–ceramic nuclear waste forms obtained by crystallization of SiO 2 –Al 2 O 3 –CaO–ZrO 2 –TiO 2 glasses containing lanthanides (Ce, Nd, Eu, Gd, Yb) and actinides (Th): Study of the crystallization from the surface显示文摘	P. Loiseau D. Caurant	2010	Journal of Nuclear Materials2010，，：	2
6	Investigation of passive films on nickel Alloy 690 in lead-containing environments显示文摘	B. Peng B.T. Lu J.L. Luo Y.C. Lu H.Y. Ma	2008	Journal of Nuclear Materials2008，，3：	2
7	Barium borosilicate glass – a potential matrix for immobilization of sulfate bearing high-level radioactive liquid waste显示文摘	C.P. Kaushik R.K. Mishra P. Sengupta Amar Kumar D. Das G.B. Kale Kanwar Raj	2006	Journal of Nuclear Materials2006，，2：	2
8	Crystallization of neodymium-rich phases in silicate glasses developed for nuclear waste immobilization显示文摘	D. Caurant O. Majerus P. Loiseau I. Bardez N. Baffier J.L. Dussossoy	2006	Journal of Nuclear Materials2006，，1：	2
9	Ferritic/martensitic steels – overview of recent results显示文摘	R.L. Klueh D.S. Gelles S. Jitsukawa A. Kimura G.R. Odette B. van der Schaaf M. Victoria	2002	Journal of Nuclear Materials2002，，：	2
10	Status and key issues of reduced activation ferritic/martensitic steels as the structural material for a DEMO blanket显示文摘		2011	Journal of Nuclear Materials2011，，1：	2
11	Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600显示文摘	J. Panter B. Viguier J.-M. Cloué M. Foucault P. Combrade E. Andrieu	2005	Journal of Nuclear Materials2005，，1：	2
12	Influence of brazing conditions on the strength of brazed joints of alumina dispersion-strengthened copper to 316 stainless steel显示文摘	H Nishi K Kikuchi	1998	Journal of Nuclear Materials1998，，：	2
13	Microstructure and impact properties of ultra-fine grained tungsten alloys dispersed with TiC显示文摘	Yuji Kitsunai Hiroaki Kurishita Hideo Kayano Yutaka Hiraoka Tadashi Igarashi Tomohiro Takida	1999	Journal of Nuclear Materials1999，，：	2
14	Microstructural examination of oxide layers formed on an oxide dispersion strengthened ferritic steel exposed to supercritical water显示文摘	Yun Chen Kumar Sridharan Todd R. Allen Shigeharu Ukai	2006	Journal of Nuclear Materials2006，，1：	2
15	Corrosion properties of oxide dispersion strengthened steels in super-critical water environment显示文摘	H.S Cho A Kimura S Ukai M Fujiwara	2004	Journal of Nuclear Materials2004，，：	2
16	Emulation of neutron irradiation effects with protons: validation of principle显示文摘	G.S Was J.T Busby T Allen E.A Kenik A Jensson S.M Bruemmer J Gan A.D Edwards P.M Scott P.L Andreson	2002	Journal of Nuclear Materials2002，，2：	2
17	Pyrochemical reduction of uranium dioxide and plutonium dioxide by lithium metal显示文摘	T Usami M Kurata T Inoue H.E Sims S.A Beetham J.A Jenkins	2002	Journal of Nuclear Materials2002，，1：	2
18	Mechanical and microstruetural properities of a hipped RAFM ODS steal显示文摘	Lindau R Moslang A Schirra M	2002	Journal of Nuclear Materials2002，，：	1
19	Microstructural evolution and hardness changes in the interface of Cu/316L joint materials under aging and ion irradiation显示文摘	Xu Q Yoshiie T Muroga T	2004	Journal of Nuclear Materials2004，，：	1
20	Correlation between characteristics of grain boundary carbides and creep-fatigue properties in AISI 321 stainless steel 显示文摘	Min K S Nam S W	2003	Journal of Nuclear Materials2003，322，：	1

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