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11篇 您的检索式:作者名="Radiguet"
    题名 作者 年代 出处 被引量
1化学成分以及辐照条件对压力容器钢中子辐照损伤的影响显示文摘在核电站反应堆中,压力容器作为压水堆的第二道安全屏障,在压水堆安全运行和防止核泄漏方面发挥着极为重要的作用。反应堆内的中子辐照会引起压力容器钢微观结构的变化,进而降低其力学性能,影响核反应堆的安全。总结了中子辐照下压力容器钢及其模型合金中形成的缺陷,并进一步综述了化学成分和中子辐照条件,包括铜、镍、磷、锰、硅和铬等元素,中子注量以及中子注量率等参数对压力容器钢中子辐照损伤的影响。黄鹤飞 RADIGUET Bertrand PAREIGE Philippe 2013材料导报2013,27,23:5
2Three-dimensional atom prohe study of irradiated, annealed and re-irradiated VVER 440 weld metals显示文摘Pareige P Radiguet B Suvorov A 2004Surf Interf Anal2004,36,56:1
3Irradiation induced cluste- ring in low copper or copper free ferritic model alloys显示文摘Radiguet B Pareige P Barbu A 2009Nucl Instrum Meth Phys Res B2009,267,89:1
4Kinetic of solute clustering in neutron irradiated ferritic model alloys and a french pressure vessel steel investigated by atom probe tomography显示文摘Meslin E Radiguet B Pareige P 2010Journal of Nuclear Materials2010,399,23:1
5Irradiation induced clustering in low copper or copper free ferritic model alloys显示文摘RADIGUET B PAREIGE P BARBY A 2009Nucl Instrum and Methods Phys Res B2009,267,:1
6Improved esthetics for the ceramometal crown显示文摘Chiche G Radiguet J Pinault A 0,,01:1
7Kinetic of solute clustering in neutron irradiated ferritic model alloys and a french pressure vessel steel investigated by atom probe tomography显示文摘Meslin E Radiguet B Pareige P 2010Journal of Nuclear Materials2010,399,23:1
8Stability of nanometer-sized oxide clusters in mechanically-alloyed steel under ion-induced displacement cascade damage conditions 显示文摘PAREIGE P MILLER M K STOLLER R E HOELZER D T CADEL E RADIGUET B 2007Journal of Nuclear Materials2007,360,2:1
9Atom probe tomography characterization of the microstructural evolution of a low copper reactor pressure vessel steel under neutron irradiation显示文摘Huang H F Radiguet B Todeschini P 2010Mater Res Soc Symp Proc2010,1264,:1
10Kinetic of solute clustering in neutron irradiated ferritic model alloys and a French pressure vessel steel investigated by atom probe tomography显示文摘Meslin E Radiguet B Pareige P 2010J Nucl Mater2010,399,23:1
11Using Microscopy to Help with the Understanding of Degradation Mechanisms Observed in Materials of Pressurized Water Reactors显示文摘Laurent Legras Alexandre Volgin Bertrand Radiguet Philippe Pareige Cedric Pokor Brigitte Decamps Thierry Couvant Nicolas Huin Romain Soulas 2017材料科学与工程(中英文B版)2017,7,5:0
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