10 – Void swelling and irradiation creep in light water reactor (LWR) environments
暂无分享,去创建一个
[1] Toshihiko Satō,et al. The synergistic influence of temperature and displacement rate on microstructural evolution of ion-irradiated Fe–15Cr–16Ni model austenitic alloy , 2007 .
[2] M. G. Burke,et al. 316 stainless steel cavity swelling in a PWR , 1995 .
[3] J. E. Flinn,et al. Residual stress behavior in fast neutron irradiated SA AISI 304l stainless steel cylindrical tubing , 1980 .
[4] D. Mosedale,et al. The effects of temperature and dose-rate variations on the creep of austenitic stainless steels in the dounreay fast reactor , 1980 .
[5] F. Garner,et al. Influence of silicon on swelling and microstructure in Russian austenitic stainless steel EI-847 irradiated to high neutron doses , 2008 .
[6] C. Woo,et al. Contribution to irradiation creep arising from gas-driven bubble growth , 1999 .
[7] David S. Gelles,et al. Neutron-Induced Swelling of Commercial Alloys at Very High Exposures , 1990 .
[8] B. M. Oliver,et al. Generation and Retention of Helium and Hydrogen in Austenitic Steels Irradiated in a Variety of LWR and Test Reactor Spectral Environments , 2002 .
[9] J. F. Bates,et al. The effect of solid transmutation products on swelling in 316 stainless steel , 1981 .
[10] W. Appleby,et al. Measurements of the effects of swelling on the Young's modulus of stainless steels , 1973 .
[11] Hiromasa Nishioka,et al. Evolution of Microstructure and Microchemistry in Cold-worked 316 Stainless Steels under PWR Irradiation , 2006 .
[12] Mychailo B. Toloczko,et al. Irradiation creep and void swelling of austenitic stainless steels at low displacement rates in light water energy systems , 1997 .
[13] E. Gilbert. IN-REACTOR CREEP OF REACTOR MATERIALS. , 1971 .
[14] F. Garner,et al. Investigation of The Synergistic Influence of Irradiation Temperature and Atomic Displacement Rate on the Microstructural Evolution of Ion-Irradiated Model Austenitic Alloy Fe-15Cr-16Ni , 2002 .
[15] Frank A. Garner,et al. Irradiation Performance of Cladding and Structural Steels in Liquid Metal Reactors , 2006 .
[16] J. Holmes,et al. Swelling and Tensile Property Evaluations of High-Fluence EBR-II Thimbles , 1973 .
[17] F. Garner,et al. Hydrogen generation arising from the59Ni(n, p) reaction and its impact on fission—fusion correlations , 1996 .
[18] F. Garner,et al. Very high swelling and embrittlement observed in a Fe–18Cr–10Ni–Ti hexagonal fuel wrapper irradiated in the BOR-60 fast reactor , 2008 .
[19] O. Maksimkin,et al. Characterization of 08Cr16Ni11Mo3 stainless steel irradiated in the BN-350 reactor , 2004 .
[20] S. Macewen,et al. In-reactor stress relaxation of selected metals and alloys at low temperatures , 1980 .
[21] Wilhelm G. Wolfer,et al. Retention of hydrogen in fcc metals irradiated at temperatures leading to high densities of bubbles or voids , 2006 .
[22] 服部 成雄,et al. 会議報告 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors , 2005 .
[23] B. M. Oliver,et al. Surprisingly Large Generation and Retention of Helium and Hydrogen in Pure Nickel Irradiated at High Temperatures and High Neutron Exposures , 2004 .
[24] F. Garner,et al. Severe embrittlement of neutron irradiated austenitic steels arising from high void swelling , 2009 .
[25] J. P. Massoud,et al. Tomographic atom probe characterization of the microstructure of a cold worked 316 austenitic stainless steel after neutron irradiation , 2008 .
[26] F. Garner,et al. Potential high fluence response of pressure vessel internals constructed from austenitic stainless steels , 1993 .
[27] Toshihiko Satō,et al. NEUTRON-INDUCED MICROSTRUCTURAL EVOLUTION OF Fe-15Cr-16Ni ALLOYS AT ~ 400°C DURING NEUTRON IRRADIATION IN THE FFTF FAST REACTOR - , 2001 .
[28] M. L. Hamilton,et al. Development of reduced activation alloys for fusion service , 1985 .
[29] B. M. Oliver,et al. The dependence of helium generation rate on nickel content of Fe-Cr-Ni alloys irradiated to high dpa levels in EBR-II , 1998 .
[30] F. Garner,et al. Irradiation creep and embrittlement behavior of AISI 316 stainless steel at very high neutron fluences , 1988 .
[31] F. Garner,et al. Determination of the Lower Temperature Limit of Void Swelling of Stainless Steels at PWR-Relevant Displacement Rates , 2004 .
[32] F. Garner. Recent insights on the swelling and creep of irradiated austenitic alloys , 1984 .
[33] F. Garner,et al. The dependence of irradiation creep in austenitic alloys on displacement rate and helium to dpa ratio , 1998 .
[34] F. Garner,et al. Unusual Enhancement of Ductility Observed During Evolution of a “Deformation Wave” in 12Cr18Ni10Ti Stainless Steel Irradiated in BN-350 , 2009 .
[35] A. Ivanov,et al. Microstructure and mechanical properties of austenitic stainless steel 12X18H9T after neutron irradiation in the pressure vessel of BR-10 fast reactor at very low dose rates , 2006 .
[36] V. Chernov,et al. The strong influence of displacement rate on void swelling in variants of Fe–16Cr–15Ni–3Mo austenitic stainless steel irradiated in BN-350 and BOR-60 , 2004 .
[37] Jean-Pierre Hugot,et al. Influence of Swelling on Irradiated CW Titanium Modified 316 Embrittlement , 1990 .
[38] C. K. Day,et al. Effect of Neutron Irradiation on the Elastic Constants of Type-304 Stainless Steel , 1973 .
[39] O. Maksimkin,et al. Void Swelling of AISI 321 Analog Stainless Steel Irradiated at Low DPA Rates in the BN-350 Reactor , 2007 .
[40] F. Garner,et al. Interaction of Void-Induced Phase Instability and Subsequent Void Growth in AISI 304 Stainless Steel , 2000 .
[41] Stephen M. Bruemmer,et al. Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS , 2003 .
[42] L. Greenwood,et al. A new calculation of thermal neutron damage and helium production in nickel , 1983 .
[43] F. Garner,et al. Nano-cavities observed in a 316SS PWR flux thimble tube irradiated to 33 and 70 dpa , 2009 .
[44] J. Foster,et al. Correlation of Inconel X750 stress relaxation data obtained in thermal and fast neutron reactors , 1988 .
[45] P. Scott,et al. An Analysis of Baffle/Former Bolt Cracking in French PWRs , 2000 .
[46] F. Garner,et al. The Effect of Void Swelling on Electrical Resistance and Elastic Moduli in Austenitic Steels , 2004 .
[47] F. Garner,et al. Anomalously large deformation of 12Cr18Ni10Ti austenitic steel irradiated to 55 dpa at 310 °C in the BN-350 reactor , 2009 .
[48] L. Mansur,et al. Low-temperature irradiation creep of fusion reactor structural materials , 1991 .
[49] F. Garner,et al. Void swelling at low displacement rates in annealed 12X18HgT stainless steel at 4–56 dpa and 280–332 °C , 2002 .