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政策工具视阈下中国养老政策分析与思考 被引量:21
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作者 孙兰英 苏长好 候光辉 《天津大学学报(社会科学版)》 2018年第4期289-295,共7页
为了对中国养老政策进行科学化研究,采用内容分析法,以政策工具视角对1949—2016年间的中共中央、国务院及相关部委的涉及养老政策规定的文本进行定量分析。研究发现,我国目前的养老政策体系存在职能过重、分布结构不合理、政策工具选... 为了对中国养老政策进行科学化研究,采用内容分析法,以政策工具视角对1949—2016年间的中共中央、国务院及相关部委的涉及养老政策规定的文本进行定量分析。研究发现,我国目前的养老政策体系存在职能过重、分布结构不合理、政策工具选择较为单一、养老政策的前瞻性和延续性较差、国家政策宏观调控与地方微观操作脱节等问题。这些问题也为未来国家制定新的养老政策带来必须高度关注和解决的课题,必须在养老领域实现政府职能转变、优化养老政策结构、完善养老政策长效机制。 展开更多
关键词 养老政策 政策分析 政策工具 政策体系
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Hardening of an ODS Ferritic Steel after Helium Implantation and Thermal Annealing
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作者 su changhao Zhang Chonghong +3 位作者 Yang Yitao Ding Zhaonan Chen Yuguang and Akihiko Kimura 《IMP & HIRFL Annual Report》 2017年第1期125-127,共3页
In advanced nuclear reactors,helium can inevitably be produced via(n,)reaction and may precipitate into nano-scale helium bubbles in materials,and can causes degradation of material properties.In the present study,eff... In advanced nuclear reactors,helium can inevitably be produced via(n,)reaction and may precipitate into nano-scale helium bubbles in materials,and can causes degradation of material properties.In the present study,effects of helium bubbles formation in an oxide dispersion strengthened(ODS)steel is studied.Specimens of an ODS ferritic steel(15Cr-4Al-0.6Zr-0.1Ti)were implanted with mutiple-energy He ions at room temperature at the terminal of the 320 kV High-voltage Platform in IMP,to create a damage plateau of 0.4 dpa for average(corresponding to an He concentration of about 7000 appm)from the near surface to a depth about 1m.The specimen was subsequently thermally annealed at 800℃for 1 h in vacuum so that simple defects formed in the as-implanted state underwent significant recombination,meanwhile helium bubbles at nano-scale were formed. 展开更多
关键词 STEEL STRENGTHENED annealed
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TEM Observation of Radiation Damage Created by Energetic Ar Ions in Silicon Carbide Fiber
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作者 Zhang Liqing Zhang Chonghong +5 位作者 Huang Qing Ding Zhaonan Chen Yuguang su changhao Zhang Xianlong Ma Baoshui 《IMP & HIRFL Annual Report》 2017年第1期123-124,共2页
Silicon carbide(SiC)fiber possesses low neutron capture cross-section,low induced radioactivity,high thermal stability,low density,high specific strength,good oxidation-ablation resistance,high specific modulus,especi... Silicon carbide(SiC)fiber possesses low neutron capture cross-section,low induced radioactivity,high thermal stability,low density,high specific strength,good oxidation-ablation resistance,high specific modulus,especially improved flaw tolerance and non-catastrophic mode of failure.Therefore,silicon carbide fiber is considered as a candidate structural component in advanced nuclear industry fields.The irradiation damage which silicon carbide fiber will be subject to is inevitable.For structural components in fast breed reactors or in fusion reactors,the energy of PKAs(primary knocked-on atoms)produced by high-energy neutron irradiation can be several hundred keV,therefore effects of energy deposition via electronic processes(excitation and ionization)by PKAs in materials cannot be ignored.In situations of fuel cladding,materials may surfer from irradiation by fission fragments(which are heavy ions with up to hundreds of MeV).It is therefore necessary to know effects of energetic heavy-ion irradiation in silicon carbide for nuclear application. 展开更多
关键词 EXCITATION MODULUS CARBIDE
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