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| 国内压水堆核电站设备材料应力腐蚀问题及安全管理 |
孙海涛,凌礼恭,吕云鹤,盛朝阳,高晨,王臣,马若群,张新,贾盼盼( ) |
| 环境保护部核与辐射安全中心 北京 100082 |
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引用本文:
孙海涛,凌礼恭,吕云鹤,盛朝阳,高晨,王臣,马若群,张新,贾盼盼. 国内压水堆核电站设备材料应力腐蚀问题及安全管理[J]. 腐蚀科学与防护技术, 2016, 28(3): 283-287.
链接本文:
https://www.cspt.org.cn/CN/Y2016/V28/I3/283
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| [1] | International Atomic Energy Agency. Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: Steam Generators, IAEA-TECDOC-981 [R]. Vienna: IAEA, 1997 | | [2] | International Atomic Energy Agency. Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety Primary Piping in PWRs, IAEA-TECDOC-1361 [R]. Vienna: IAEA, 2003 | | [3] | Nuclear Regulatory Commission.Investigation and Evaluation of Stress Corrosion Cracking in Piping of Light Water Reactor Plants,NUREG-0531 [R]. Washington, DC: U.S. NRC, 1979 | | [4] | International Atomic Energy Agency. Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: BWR Pressure Vessels, IAEA-TECDOC-1470 [R]. Vienna: IAEA, 2005 | | [5] | International Atomic Energy Agency. Stress Corrosion Cracking in Light Water Reactors: Good Practices and Lessons Learned, NP-T-3.13 [R]. Vienna: IAEA, 2011 | | [6] | Nuclear Regulatory Commission.Technical report on material selection and processing guidelines for BWR coolant pressure boun-dary piping, NUREG-0313 [R]. Washington, DC: U.S. NRC, 1988 | | [7] | American Society of Mechanical Engineers. Rules for in-service inspection of nuclear power plant components[S]. New York, 2004 | | [8] | 段远刚. 围板连接螺栓的辐照促进应力腐蚀裂纹研究[J]. 核动力工程, 2007, 28(2): 62 | | [9] | 操丰. 核电厂换料水池304L不锈钢覆面开裂原因分析[J]. 核动力工程, 2014, 35(2): 150 | | [10] | AFCEN. Design and construction rules for mechanical components of PWR nuclear islands[S]. Paris, 1997 | | [11] | 朱志平. 690合金在ETA和AVT水工况下的电化学性能[J]. 腐蚀科学与防护技术, 2012, 24(4): 285 | | [12] | 郦晓慧. 核级商用690合金和800合金在模拟压水堆核电站一回路高温高压水中的腐蚀行为研究[J]. 金属学报, 2012, 48(8): 941 | | [13] | 刘影恬. Incoloy 800与Inconel 690抗腐蚀性能研究现状[J]. 科技资讯, 2014, 12(23): 90 | | [14] | 但体纯. 压水堆核电站蒸汽发生器用600合金管在含铅高温碱溶液中的应力腐蚀行为研究[J]. 腐蚀科学与防护技术, 2008, 20(5): 313 | | [15] | 刘自军. 压水堆核电站核岛主设备焊接制造工艺及窄间隙焊接技术[J]. 电焊机, 2010, 40(2): 10 | | [16] | Damico T.The applicability of MSIP? for mitigating PWSCC in pressurizer nozzle to safe-endwelds [R]. New Mexico: EPRI, 2005 | | [17] | 乔培鹏. 压水堆条件下锌对奥氏体不锈钢腐蚀性能的影响[J]. 原子能科学技术, 2010, 44(6): 690 | | [18] | 李衍. 应力腐蚀裂纹的超声检测和定量—相控阵超声 (PAUT) 技术应用案例[J]. 无损探伤, 2012, 36(5): 1 | | [19] | 魏敏. 核压力容器接管安全端堆焊修复对失效评定曲线的影响[J]. 压力容器, 2013, 30(5): 58 | | [20] | Zhang T, Brust F W.Weld resdiual stress analysis and the effects of structural overlay on various nuclear power plant nozzles[J]. J. Pressure Vessel Technol., 2012, 134(6) |
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