Thermal Fatigue of Zircaloy-4 Cladded U-7.5Nb-2.5Zr
暂无分享,去创建一个
[1] C. G. Schön,et al. Laves phases in the U – Mo – Zr system , 2020 .
[2] D. A. Lopes,et al. Effect of thermo-mechanical processing on microstructure and mechanical properties of U – Nb – Zr alloys: Part 2 - U – 3 wt % Nb – 9 wt % Zr and U – 9 wt% Nb – 3 wt% Zr , 2018 .
[3] Kenta Murakami,et al. Current status of materials development of nuclear fuel cladding tubes for light water reactors , 2017 .
[4] D. A. Lopes,et al. Effect of thermo-mechanical processing on microstructure and mechanical properties of U – Nb – Zr alloys: Part 1 - U–6 wt % Nb –6 wt % Zr , 2017 .
[5] J. Piqueira,et al. Thermal cycling effect in U-10Mo/Zry-4 monolithic nuclear fuel , 2016 .
[6] S. McDeavitt,et al. Decomposition of the γ phase in as-cast and quenched U-Zr alloys , 2016 .
[7] Xianglin Chen,et al. Effect of grain size on phase stability of monoclinic U–Nb alloy during low-temperature aging , 2015 .
[8] Arthur T. Motta,et al. Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding , 2015 .
[9] S. Kaity,et al. Microstructural investigation of uranium rich U–Zr–Nb ternary alloy system , 2014 .
[10] A. F. Padilha,et al. Mechanical and thermal behaviour of U–Mo and U–Nb–Zr Alloys , 2013 .
[11] N. Prabhu,et al. On the formation mechanism of UZr2 phase , 2010 .
[12] R. Mccabe,et al. Deformation of wrought uranium: Experiments and modeling , 2010 .
[13] H. S. Liu,et al. Thermodynamic assessment of the U–Mo–Al system , 2010 .
[14] Douglas E. Burkes,et al. Properties of DU–10 wt% Mo alloys subjected to various post-rolling heat treatments ☆ , 2010 .
[15] H. S. Kamath,et al. An evaluation of the properties of As-cast U-rich U–Zr alloys , 2009 .
[16] Douglas E. Burkes,et al. Mechanical Properties of DU-xMo Alloys with x = 7 to 12 Weight Percent , 2009 .
[17] Dan Thoma,et al. X-ray diffraction analyses of aged U–Nb alloys , 2007 .
[18] A. Kimura,et al. High Burnup Fuel Cladding Materials R&D for Advanced Nuclear Systems , 2007 .
[19] Yong Hwan Jeong,et al. Oxidation kinetics of Zircaloy-4 and Zr–1Nb–1Sn–0.1Fe at temperatures of 700–1200 °C , 2004 .
[20] T. Terai,et al. Heat capacities of uranium-zirconium alloys from 300 to 1100 K , 1989 .
[21] A. Pelton,et al. Thermodynamics of the uranium-zirconium system , 1989 .
[22] W. M. Justusson. TRANSFORMATION KINETICS OF GAMMA-PHASE URANIUM-MOLYBDENUM-NIOBIUM ALLOYS , 1961 .
[23] W. S. Blackburn. α−β Thermal cycling of uranium , 1960 .
[24] J. J. Stobo. Alpha beta cycling of uranium , 1960 .
[25] T. Heltemes,et al. Transitional cores and fuel cycle analyses in support of MIT reactor low enriched uranium fuel conversion , 2020 .
[26] Xiaolin Wang,et al. X-ray diffraction study of low temperature aging in U–5.8 wt.%Nb , 2015 .
[27] R. Cahn,et al. Plastic deformation of alpha-uranium; twinning and slip , 1953 .