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434                                     摩   擦   学   学   报                                 第 41 卷

                 Zircaloy-4  and  M5®[J].  Journal  of  Nuclear  Materials,  2015,  467:  [40]  Jiang  H,  Duan  Z,  zhang  B,  et  al.  Fretting  wear  behaviors  of  Zr-4
                 785–801. doi: 10.1016/j.jnucmat.2015.10.009.      alloy  under  different  ions  irradiation  conditions[J].  Tribology
            [29]  Iqbal M, Akhter J I, Zhang H F, et al. Synthesis and characterization  International,  2020,  152:  106553.  doi:  10.1016/j.triboint.2020.
                 of  bulk  amorphous  steels[J].  Journal  of  Non-Crystalline  Solids,  106553.
                 2008, 354(28): 3284–3290. doi: 10.1016/j.jnoncrysol.2008.02.009.  [41]  Wang  Peng,  Chai  Liqiang,  Zhao  Xiaoyu,  et  al.  Friction,  wear  and
            [30]  Tournadre L, Onimus F, Béchade J L, et al. Experimental study of  lubrication  in  nuclear  environments[J].  Tribology,  2020,  40(4):
                 the  nucleation  and  growth  of  c-component  loops  under  charged  489–503 (in Chinese) [王鹏, 柴利强, 赵晓宇, 等. 核环境下的摩
                 particle  irradiations  of  recrystallized  Zircaloy-4[J].  Journal  of  擦 、 磨 损 与 润 滑 [J].  摩 擦 学 学 报 ,  2020,  40(4):  489–503].  doi:
                 Nuclear  Materials,  2012,  425(1-3):  76–82.  doi:  10.1016/j.jnucmat.  10.16078/j.tribology.2020071.
                 2011.11.061.                                  [42]  Song  Lijun,  Liu  Feihua,  Li  Chengtao,  et  al.  Effect  of  B-Li  water
            [31]  Shen Huahai. Radiation damage and helium bubble evolution in A  chemistry on corrosion of metal materials of nuclear power plant[J].
                 zirconium alloy[D]. Chengdu: University of Electronic Science and  Nuclear  Science  and  Engineering,  2014,  34(1):  97–101+115
                 Technology of China, 2015 (in Chinese) [申华海. 锆合金带电离子  (in Chinese) [宋利君, 刘飞华, 李成涛, 等. B-Li水化学对核电站金
                 辐照效应及氦泡演化行为研究[D]. 成都: 电子科技大学, 2015].              属材料腐蚀的影响[J]. 核科学与工程, 2014, 34(1): 97–101+115].
            [32]  Zhang Chonghong. Damage production by inert-gas-ion irradiation  [43]  Sridharan  K.  Understanding  how  materials  corrode  in  nuclear
                 in  some  candidate  materials  to  fusion  reactors[J].  Nuclear  Physics  reactors[J]. Advanced Materials & Processes, 2014, 172(1): 17–20.
                 Review, 2006, (2): 167–169 (in Chinese) [张崇宏. 聚变堆候选金属  [44]  Wei  Kejian,  Xue  Wenbin,  Qu  Yao,  et  al.  Advance  in  microarc
                 材料的惰性气体离子辐照损伤的研究[J]. 原子核物理评论, 2006,               oxidation  surface  treatment  on  Zr[J].  Surface  Technology,  2019,
                 (2): 167–169]. doi: 10.3969/j.issn.1007-4627.2006.02.019.  48(7): 11–23 (in Chinese) [魏克俭, 薛文斌, 曲尧, 等. 锆微弧氧化
            [33]  Neogy S, Mukherjee P, Srivastava A P, et al. Proton irradiation of  表面处理技术研究进展[J]. 表面技术, 2019, 48(7): 11–23]. doi:
                 Zr-1wt.%  Nb  cladding  material:  A  depth-wise  assessment  of  10.16490/j.cnki.issn.1001-3660.2019.07.002.
                 inhomogeneous microstructural damage using X-ray diffraction line  [45]  Liu  J,  Mir  A  H,  He  G,  et  al.  In-situ  TEM  study  of  irradiation-
                 profile  analyses[J].  Journal  of  Alloys  and  Compounds,  2015,  640:  induced  damage  mechanisms  in  monoclinic-ZrO 2 [J].  Acta
                 175–182. doi: 10.1016/j.jallcom.2015.04.016.      Materialia, 2020, 199: 429–442. doi: 10.1016/j.actamat.2020.08.064.
            [34]  Abromeit  C.  Aspects  of  simulation  of  neutron  damage  by  ion  [46]  Aidhy D S, Zhang Y, Weber W J. Radiation damage in cubic ZrO 2
                 irradiation[J]. Journal of Nuclear Materials, 1994, 216: 78–96. doi:  and   yttria-stabilized   zirconia   from   molecular   dynamics
                 10.1016/0022-3115(94)90008-6.                     simulations[J].  Scripta  Materialia,  2015,  98:  16–19.  doi:  10.1016/
            [35]  Sarkar  A,  Mukherjee  P,  Barat  P.  Characterization  of  irradiated  j.scriptamat.2014.10.036.
                 microstructure  by  X-ray  diffraction  line  profile  analysis[J].  [47]  Ingo  G  M,  Marletta  G.  Ion  beam  induced  reduction  of  metallic
                 Metallurgical  and  Materials  Transactions  A,  2008,  39(7):  cations  in  yttria-zirconia[J].  Nuclear  Instruments  and  Methods  in
                 1602–1609. doi: 10.1007/s11661-007-9428-7.        Physics Research Section B: Beam Interactions with Materials and
            [36]  Cao Shuang, Yu Qingkui, Zheng Xuefeng, et al. Failure analysis on  Atoms,  1996,  116(1-4):  440–446.  doi:  10.1016/0168-583X(96)
                 leakage current degradation of heavy-ion-irradiated 1200 V silicon  00085-7.
                 carbide  diodes[J].  Equipment  Environmental  Engineering,  2020,  [48]  Yeom  H,  Maier  B,  Johnson  G,  et  al.  Development  of  cold  spray
                 17(3): 53–58 (in Chinese) [曹爽, 于庆奎, 郑雪峰, 等. 重离子辐照  process  for  oxidation-resistant  FeCrAl  and  Mo  diffusion  barrier
                                                                                      TM
                 1200 V碳化硅二极管漏电退化的缺陷分析[J]. 装备环境工程,                 coatings  on  optimized  ZIRLO [J].  Journal  of  Nuclear  Materials,
                 2020, 17(3): 53–58].                              2018, 507: 306–315. doi: 10.1016/j.jnucmat.2018.05.014.
            [37]  Han  J  G,  Lee  J  S,  Kim  W,  et  al.  Zirconium  oxide  formation  and  [49]  Azevedo  C  R  F.  Selection  of  fuel  cladding  material  for  nuclear
                 surface hardening behavior by nitrogen implantation under oxygen  fission  reactors[J].  Engineering  Failure  Analysis,  2011,  18(8):
                 atmosphere  in  Zircaloy-4[J].  Surface  and  Coatings  Technology,  1943–1962. doi: 10.1016/j.engfailanal.2011.06.010.
                 1997, 97(1-3): 492–498. doi: 10.1016/S0257-8972(97)00162-X.  [50]  Raepsaet  C,  Bossis  P,  Hamon  D,  et  al.  Quantification  and  local
            [38]  Yu  Bo.  Irradiation  effects  of  low-energy  ions  on  a  zirconium  distribution  of  hydrogen  within  Zircaloy-4  PWR  nuclear  fuel
                 alloy[D]. Harbin: Harbin Institute of Technology, 2012 (in Chinese)  cladding  tubes  at  the  nuclear  microprobe  of  the  Pierre  Süe
                 [禹博. 锆基合金低能离子辐照效应研究[D]. 哈尔滨: 哈尔滨工业                Laboratory from μ-ERDA[J]. Nuclear Instruments and Methods in
                 大学, 2012].                                        Physics Research Section B: Beam Interactions With Materials and
            [39]  Zhang  Hongpeng.  Effects  of  charged  particles  irradiation  on  Atoms,  2008,  266(10):  2424–2428.  doi:  10.1016/j.nimb.2008.03.
                 microstructure and properties of Zr-702[D]. Harbin: Harbin Institute  041.
                 of Technology, 2011 (in Chinese) [张宏鹏. 带电粒子辐照对Zr-  [51]  Ni  N,  Lozano-Perez  S,  Jenkins  M  L,  et  al.  Porosity  in  oxides  on
                 702组织和性能的影响[D]. 哈尔滨: 哈尔滨工业大学, 2011].              zirconium  fuel  cladding  alloys,  and  its  importance  in  controlling
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