[1]
|
李佩志. 我国锆合金的研究现状[J]. 稀有金属材料与工程, 1993, 22(4): 7-16.
|
[2]
|
王旭峰, 李中奎, 周军, 等. 锆合金在核工业中的应用及研究进展[J]. 热加工工艺, 2012, 41(2): 71-74.
|
[3]
|
赵文金, 周邦新, 苗志, 等. 我国高性能锆合金的发展[J]. 原子能科学与技术2005, 39(Sl): 2-9.
|
[4]
|
吴璐, 邱绍宇, 伍晓勇, 等. 中子辐照对锆合金显微组织的影响研究进展[J]. 重庆大学学报, 2017, 40(4): 24-34.
|
[5]
|
黄强. 锆合金耐腐蚀性能研究综述[J]. 核动力工程, 1996, 17(3): 262-267.
|
[6]
|
李中奎, 刘建章, 周廉, 等. 新锆合金耐腐蚀性能研究[J]. 原子能科学技术, 2003, 37(Sl): 84-87.
|
[7]
|
王辉, 胡石林, 杨启法, 等. 国产新型锆铌合金水侧腐蚀行为研究[J]. 原子能科学技术, 2007, 41(Sl): 342-347.
|
[8]
|
吴璐, 张伟, 徐春容, 等. 电解渗氢对N18和Zr-4合金板材中氢化物的影响[J]. 材料保护, 2016, 49(Sl): 23-26.
|
[9]
|
Yamanaka, S., Miyake, M. and Katsura, M. (1997) Study on the Hydrogen Solubility in Zirconium Alloys. Journal of Nuclear Materials, 247, 315-321. https://doi.org/10.1016/S0022-3115(97)00101-3
|
[10]
|
Wäppling, D., Massih, A.R. and Stahel, P. (1997) A Model for Hydride-Induced Embrittlement in Zirconium-Based Alloys. Journal of Nuclear Materials, 249, 231-238. https://doi.org/10.1016/S0022-3115(97)00183-9
|
[11]
|
Ackland, G.J. (1998) Embrittlement and Bistable Crystal Structure of Zirconium Hydride. Physical Review Letters, 80, 2233-2236. https://doi.org/10.1103/PhysRevLett.80.2233
|
[12]
|
Varias, A.G. and Massih, A.R. (2000) Simulation of Hydrogen Embrittlement in Zirconium Alloys under Stress and Temperature Gradients. Journal of Nuclear Materials, 279, 273-285. https://doi.org/10.1016/S0022-3115(99)00286-X
|
[13]
|
Zhang, Y.F., Bai, X.M., Yu, J.G., et al. (2016) Homogeneous Hydride Formation Path in α-Zr: Molecular Dynamics Simulations with the Charge-Optimized Many-Body Potential. Acta Materialia, 111, 357-365. https://doi.org/10.1016/j.actamat.2016.03.079
|
[14]
|
Muta, H., Nishikane, R., Ando, Y., et al. (2018) Effect of Hydrogenation Conditions on the Microstructure and Mechanical Properties of Zirconium Hydride. Journal of Nuclear Materials, 500, 145-152. https://doi.org/10.1016/j.jnucmat.2017.12.027
|
[15]
|
Silva, C.M., Leonard, K.J., Abel, E.V., et al. (2018) Investi-gation of Mechanical and Microstructural Properties of Zircaloy-4 under Different Experimental Conditions. Journal of Nuclear Materials, 499, 546-557. https://doi.org/10.1016/j.jnucmat.2017.12.012
|
[16]
|
Une, K., Ishimoto, S., Etoh, Y., et al. (2009) The Terminal Solid Solubility of Hydrogen in Irradiated Zircaloy-2 and Microscopic Modeling of Hy-dride Behavior. Journal of Nuclear Materials, 389, 127-136. https://doi.org/10.1016/j.jnucmat.2009.01.017
|
[17]
|
Zhu, W.H., Wang, R.S., Shu, G.G., Wu, P. and Xiao, H.M. (2010) First-Principles of Study of Different Polymorphs of Crystalline Zirconium Hydride. Journal of Physical Chemistry C, 114, 22361-22368. https://doi.org/10.1021/jp109185n
|
[18]
|
Wang, F. and Gong, H.R. (2012) Me-chanical and Structural Stability of Zirconium Dihydride. International Journal of Hydrogen Energy, 37, 9688-9695. https://doi.org/10.1016/j.ijhydene.2012.03.078
|
[19]
|
Lumley, S.C., Grimes, R.W., Murphy, S.T., Burr, P.A., Chroneos, A., Chard-Tuckey, P.R. and Wenman, M.R. (2014) The Thermodynamics of Hydride Precipitation: The Importance of Entropy, Enthalpy and Disorder. Acta Materiialia, 79, 351-362. https://doi.org/10.1016/j.actamat.2014.07.019
|
[20]
|
Christensen, M., Wolf, W., Freeman, C., Wimmer, E., Adamson, R.B., Hallstadius, L., Cantonwine, P.E. and Mader, E.V. (2015) H in α-Zr and Zirconium Hydrides: Solubility, Effect on Dimensional Changes, and the Role of Defects. Journal of Physics: Condensed Matter, 27, Article ID: 025402. https://doi.org/10.1088/0953-8984/27/2/025402
|
[21]
|
Bair, J., Zaeem, M.A. and Schwen, D. (2017) Formation Path of δ-Hydrides in Zirconium by Multiphase Field Modeling. Acta Materialia, 123, 235-244. https://doi.org/10.1016/j.actamat.2016.10.056
|
[22]
|
Sharma, R.K., Tewari, A., Singh, R.N., et al. (2018) Optimum Shape and Orientation of δ-Hydride Precipitate in α-Zirconium Matrix for Different Temperatures. Journal of Alloys and Compounds, 742, 804-813. https://doi.org/10.1016/j.jallcom.2017.12.085
|
[23]
|
Burr, P.A., Murphy, S.T., Lumley, S.C., et al. (2013) Hydrogen Accommodation in Zr Second Phase Particles: Implications for H Pick-Up and Hydriding of Zircaloy-2 and Zircaloy-4. Corrosion Science, 69, 1-4. https://doi.org/10.1016/j.corsci.2012.11.036
|
[24]
|
Blackmur, M.S., Robson, J.D., Preuss, M., et al. (2015) Zirco-nium Hydride Precipitation Kinetics in Zircaloy-4 Observed with Synchrotron X-Ray Diffraction. Journal of Nuclear Materials, 464, 160-169. https://doi.org/10.1016/j.jnucmat.2015.04.025
|
[25]
|
Chu, H.C., Wu, S.K., Chen, K.F., et al. (2007) Effect of Radial Hydrides on the Axial and Hoop Mechanical Properties of Zircaloy-4 Cladding. Journal of Nuclear Materials, 362, 93-103. https://doi.org/10.1016/j.jnucmat.2006.11.008
|
[26]
|
Kerr, M., Daymond, M.R., Holt, R.A., et al. (2008) Strain Evolution of Zirconium Hydride Embedded in a Zircaloy-2 Matrix. Journal of Nuclear Materials, 380, 70-75. https://doi.org/10.1016/j.jnucmat.2008.07.004
|
[27]
|
Steuwer, A., Santisteban, J.R., Preuss, M., et al. (2009) Evidence of Stress-Induced Hydrogen Ordering in Zirconium Hydrides. Acta Materialia, 57, 145-152. https://doi.org/10.1016/j.actamat.2008.08.061
|
[28]
|
Colas, K.B., Motta, A.T., Almer, J.D., et al. (2010) In Situ Study of Hydride Precipitation Kinetics and Re-Orientation in Zircaloy Using Synchrotronradiation. Acta Materialia, 58, 6575-6583. https://doi.org/10.1016/j.actamat.2010.07.018
|
[29]
|
Qin, W., Kiran Kumar, N.A.P., Szpunar, J.A., et al. (2011) Intergranular δ-Hydride Nucleation and Orientation in Zirconium Alloys. Acta Materialia, 59, 7010-7021. https://doi.org/10.1016/j.actamat.2011.07.054
|
[30]
|
Hsu, H.-H. and Tsay, L.-W. (2011) Effect of Hydride Orien-tation on Fracture Toughness of Zircaloy-4 Cladding. Journal of Nuclear Materials, 408, 67-72. https://doi.org/10.1016/j.jnucmat.2010.10.068
|
[31]
|
Grosse, M., van den Berg, M., Goulet, C., et al. (2011) In-Situ Neutron Radiography Investigations of Hydrogen Diffusion and Absorption in Zirconium Alloys. Nuclear Instruments and Methods in Physics Research A, 651, 253-257. https://doi.org/10.1016/j.nima.2010.12.070
|
[32]
|
Motia, A.T. and Chen, L.O. (2012) Hydride Formation in Zirconium Alloys. Journal of Metals, 64, 1403-1408. https://doi.org/10.1007/s11837-012-0479-x
|
[33]
|
Couet, A., Motta, A.T. and Comstock, R.J. (2015) Effect of Alloying Elements on Hydrogen pickup in Zirconium. Zirconium in the Nuclear Industry: 17th International Symposium, Hyderabad, 3-7 February 2013, STP 1543, 479. https://doi.org/10.1520/STP154320120215
|
[34]
|
彭剑超, 李强, 刘仁多, 等. Zr-4合金中氢化物析出长大的透射电镜原位研究[J]. 稀有金属材料与工程, 2011, 40(8): 1377-1381.
|
[35]
|
Glazoff, M.V., Tokuhiro, A., Rashkeev, S.N., et al. (2014) Oxidation and Hydrogen Uptake in Zirconium, Zircaloy-2 and Zircaloy-4: Computational Thermodynamics and Ab Initio Caculations. Journal of Nuclear Materials, 444, 65-75. https://doi.org/10.1016/j.jnucmat.2013.09.038
|
[36]
|
Wang, Z., Zhou, B.X., Pan, R.J., et al. (2019) Stress-Driven Grain Re-Orientation and Merging Behaviour Found in Oxidation of Zirconium Alloy Using In-Situ Method and MD Simulation. Corrosion Science, 147, 350-356. https://doi.org/10.1016/j.corsci.2018.11.034
|
[37]
|
Stojilovic, N., Bender, E.T. and Ramsier, R.D. (2006) Oxidation of Zircaloy-4 by Oxygen and the Production of Water. Journal of Nuclear Materials, 348, 79-86. https://doi.org/10.1016/j.jnucmat.2005.08.022
|
[38]
|
Yilmazbayhan, A., Breval, E., Motta, A.T., et al. (2006) Transmission Electron Microscopy Examination of Oxide Layers Formed on Zralloys. Journal of Nuclear Materials, 349, 265-281. https://doi.org/10.1016/j.jnucmat.2005.10.012
|
[39]
|
Qin, W., Nam, C., Li, H.L., et al. (2007) Tetragonal Phase Stability in ZrO2 Film Formed on Zirconium Alloys and Its Effects on Corrosion Resistance. Acta Materialia, 55, 1695-1701. https://doi.org/10.1016/j.actamat.2006.10.030
|
[40]
|
Ma, X., Toffolon-Masclet, C., Guilbert, T., et al. (2008) Oxidation Kinetics and Oxgen Diffusion in Low-Tin Zircaloy-4 up to 1523 K. Journal of Nuclear Materials, 27, 359-369. https://doi.org/10.1016/j.jnucmat.2008.03.012
|
[41]
|
Ni, N., Lozano-Perez, S., Jenkins, M.L., et al. (2010) Porosity in Oxides on Zirconium Fuel Cladding Alloys, and Its Importance in Controlling Oxidationrates. Scripta Materialia, 62, 564-567. https://doi.org/10.1016/j.scriptamat.2009.12.043
|
[42]
|
Tejland, P. and Andrén, H.-O. (2012) Origin and Effect of Lateral Cracks in Oxide Scales Formed on Zirconium Alloys. Journal of Nuclear Materials, 430, 64-71. https://doi.org/10.1016/j.jnucmat.2012.06.039
|
[43]
|
Mallipudi, V.R., Valance, S. and Bertsch, J. (2012) Meso-Scale Analysis of the Creep Behavior of Hydrogenated Zircaloy-4. Mechanics of Materials, 51, 15-28. https://doi.org/10.1016/j.mechmat.2012.03.003
|
[44]
|
Dunlop, J.W., Bréchet, Y.J.M., Legras, L., et al. (2007) Dislocation Density-Based Modelling of Plastic Deformation of Zircaloy-4. Materials Science and Engineering A, 443, 77-86. https://doi.org/10.1016/j.msea.2006.08.085
|
[45]
|
Tulkki, V. and Ikonen, T. (2015) Viscoelastic Modelling of Zircaloy Cladding In-Pile Transient Creep. Journal of Nuclear Materials, 457, 324-329. https://doi.org/10.1016/j.jnucmat.2014.11.100
|
[46]
|
Moon, J.H., Cantonwine, P.E., Anderson, K.R., et al. (2006) Characterization and Modeling of Creep Mechanisms in Zircaloy-4. Journal of Nuclear Materials, 353, 177-189. https://doi.org/10.1016/j.jnucmat.2006.01.023
|
[47]
|
Hayes, A., Rosen, R.S. and Kassner, M.E. (2006) Creep Fracture of Zirconium Alloys. Journal of Nuclear of Materials, 353, 109-118. https://doi.org/10.1016/j.jnucmat.2006.02.093
|
[48]
|
Hayes, T.A. and Eassner, M.E. (2006) Creep of Zirconium and Zirconium Alloys. Metallurgical and Materials Transaction A, 37, 2389-2396. https://doi.org/10.1007/BF02586213
|
[49]
|
Morrow, B.M., Kozar, R.W., Anderson, K.R., et al. (2013) An Exam-ination of the Use of the Modified Jogged-Screw Model for Predicting Creep Behavior in Zircaloy-4. Acta Materialia, 61, 4452-4460. https://doi.org/10.1016/j.actamat.2013.04.014
|
[50]
|
Massih, A.R. (2013) High-Temperature Creep and Superplasticity in Zirconium Alloys. Journal of Nuclear Science and Technology, 1, 21-34. https://doi.org/10.1080/00223131.2013.750054
|
[51]
|
Sarkar, A., Boopathy, K., Eapen, J., et al. (2014) Creep Be-havior of Hydrogenated Zirconium Alloys. Journal of Materials Engineering and Performance, 23, 3649-3656. https://doi.org/10.1007/s11665-014-1129-y
|
[52]
|
Kozar, R.W., Jaworski, A.W., Webb, T.W., et al. (2014) In Situ Monitored In-Pile Creep Testing of Zirconium Alloys. Journal of Nuclear Materials, 444, 14-22. https://doi.org/10.1016/j.jnucmat.2013.08.043
|
[53]
|
Kombaiah, B. and LingaMurty, K. (2015) Dislocation Cross-Slip Controlled Creep in Zircaloy-4 at High Stresses. Materials Science & Engineering A, 623, 114-123. https://doi.org/10.1016/j.msea.2014.11.040
|