Page 33 - 《爆炸与冲击》2026年第10期
P. 33

第 46 卷   叶想平,等: 辐照-预应力和冲击耦合作用下金属硬化和脆化规律与微观机理实验研究进展                             第 10 期

                     Materials, 2007, 371: 145–160.
               [67]   MILLER M K, RUSSELL K F, KOCIK J, et al. Embrittlement of low copper VVER 440 surveillance samples neutron-
                     irradiated to high fluences [J]. Journal of Nuclear Materials, 2000, 282(1): 83–88.
               [68]   邓平, 彭群家, 韩恩厚, 等. 国产核用不锈钢辐照损伤研究 [J]. 金属学报, 2017, 53(12): 1588–1602. DOI: 10.11900/
                     0412.1961.2017.00117.
                     DENG P, PENG Q J, HAN E H, et al. Study of irradiation damage in domestically fabricated nuclear grade stainless steel [J].
                     Acta Metallurgica Sinica, 2017, 53(12): 1588–1602. DOI: 10.11900/0412.1961.2017.00117.
               [69]   XIA T J, JIANG Z Y, WANG Z Z, et al. Interaction between hydrogen and helium in tungsten successively exposed by
                     helium and hydrogen plasma [J]. Journal of Nuclear Materials, 2023, 574: 154184. DOI: 10.1016/j.jnucmat.2022.154184.
               [70]   SHANG Z X, NIU T J, SUN T Y, et al. In situ study on radiation response of a nanotwinned steel [J]. Scripta Materialia,
                     2022, 220: 114920. DOI: 10.1016/j.scriptamat.2022.114920.
               [71]   BEYERLEIN I J, CARO A, DEMKOWICZ M J, et al. Radiation damage tolerant nanomaterials [J]. Materials Today, 2013,
                     16(11): 443–449. DOI: 10.1016/j.mattod.2013.10.019.
               [72]   ODETTE G R, HOELZER D T. Irradiation-tolerant nanostructured ferritic alloys: transforming helium from a liability to an
                     asset [J]. JOM, 2010, 62(9): 84–92. DOI: 10.1007/s11837-010-0144-1.
               [73]   DIAO S Z, ZHAO Q, WANG S L, et al. The microstructure evolution and irradiation hardening in 15Cr-ODS steel irradiated
                     by helium ions [J]. Materials Characterization, 2022, 184: 111699. DOI: 10.1016/j.matchar.2021.111699.
               [74]   SHEN J J, NAGASAKA T, MUROGA T, et al. Study on anisotropy in microstructure and tensile properties of the 12Cr
                     oxide  dispersion  strengthened  (ODS)  steel  [J].  Fusion  Engineering  and  Design,  2019,  146:  1082–1085.  DOI:  10.1016/j.
                     fusengdes.2019.02.011.
               [75]   JIAO Z, WAS G S. The role of irradiated microstructure in the localized deformation of austenitic stainless steels [J]. Journal
                     of Nuclear Materials, 2010, 407(1): 34–43. DOI: 10.1016/j.jnucmat.2010.07.006.
               [76]   叶想平, 李英雷, 翁继东, 等. 颗粒增强金属基复合材料的强化机理研究现状 [J]. 材料工程, 2018, 46(12): 28–37. DOI:
                     10.11868/j.issn.1001-4381.2016.001214.
                     YE  X  P,  LI  Y  L,  WENG  J  D,  et  al.  Research  status  on  strengthening  mechanism  of  particle-reinforced  metal  matrix
                     composites [J]. Journal of Materials Engineering, 2018, 46(12): 28–37. DOI: 10.11868/j.issn.1001-4381.2016.001214.
               [77]   OROWAN E. In symposium on internal stresses in metals and alloys [R]. London: Institute of Metals, 1948: 451.
               [78]   KIM J H, LEE M G, KIM D, et al. Micromechanics-based strain hardening model in consideration of dislocation-precipitate
                     interactions [J]. Metals and Materials International, 2011, 17(2): 291–300. DOI: 10.1007/s12540-011-0417-4.
               [79]   LUPPO M I, BAILAT C, SCHÄUBLIN R, et al. Tensile properties and microstructure of 590 MeV proton-irradiated pure Fe
                     and a Fe-Cr alloy [J]. Journal of Nuclear Materials, 2000, 283/284/285/286/287: 483–487. DOI: 10.1016/s0022-3115(00)
                     00370-6.
               [80]   LUFT A. Microstructural processes of plastic instabilities in strengthened metals [J]. Progress in Materials Science, 1991,
                     35(2): 97–204. DOI: 10.1016/0079-6425(91)90002-B.
               [81]   SINGH B N, ZINKLE S J. Defect accumulation in pure fcc metals in the transient regime: a review [J]. Journal of Nuclear
                     Materials, 1993, 206(2/3): 212–229. DOI: 10.1016/0022-3115(93)90125-I.
               [82]   WAS  G  S,  FARKAS  D,  ROBERTSON  I  M.  Micromechanics  of  dislocation  channeling  in  intergranular  stress  corrosion
                     crack nucleation [J]. Current Opinion in Solid State and Materials Science, 2012, 16(3): 134–142. DOI: 10.1016/j.cossms.2012.
                     03.003.
               [83]   COTTRELL A H, STOKES R J. Effects of temperature on the plastic properties of aluminium crystals [J]. Proceedings of the
                     Royal Society of London. Series A: Mathematical and Physical Sciences, 1955, 233(1192): 17–34. DOI: 10.1098/rspa.1955.
                     0243.
               [84]   PENG S Y, JIN K, YI X, et al. Mechanical behavior of the HfNbZrTi high entropy alloy after ion irradiation based on micro-
                     pillar compression tests [J]. Journal of Alloys and Compounds, 2022, 892: 162043. DOI: 10.1016/j.jallcom.2021.162043.
               [85]   SADEGHILARIDJANI M, AYYAGARI A, MUSKERI S, et al. Ion irradiation response and mechanical behavior of reduced
                     activity high entropy alloy [J]. Journal of Nuclear Materials, 2020, 529: 151955. DOI: 10.1016/j.jnucmat.2019.151955.


                                                         101101-17
   28   29   30   31   32   33   34   35   36   37   38