期刊文献+

热-辐照联合老化电缆的压入模量性能研究 被引量:5

Study on Indenter Modulus of Cables under Thermal-radiation Ageing
下载PDF
导出
摘要 将两种核安全级电缆进行热-辐照联合老化试验,并对其老化后的压入模量和断裂伸长率进行测试,获得了电缆护套压入模量、断裂伸长率与老化的关系曲线。分析电缆护套的压入模量与老化的关系、不同老化速率对压入模量老化跟踪性的影响、以及压入模量与断裂伸长率的老化跟踪性的异同。结果表明:压入模量对于电缆B护套的老化跟踪性更好。由于具有无损性、定量性、对某些材料的老化跟踪性好等优点,压入模量可作为一种电缆状态指标。 Two 1E cable sheaths were conducted thermal-radiation ageing experiments, and their indenter modulus and elongation at break were tested, and then the relationship between indenter modulus, elongation at break and ageing was obtained. The relationship between indenter modulus and ageing, the effects of ageing rate on the ageing tracking performance of indenter modulus, and the ageing tracking performance difference between indenter modulus and elongation at break were analyzed. The results show that the indenter modulus has better ageing tracking performance for the cable B sheath. Because the indenter modulus has non-destructivity, quantitative feature, and good ageing tracking performance for certain kinds of material, it could be as a state indicator for cable.
出处 《绝缘材料》 CAS 北大核心 2016年第5期46-48,54,共4页 Insulating Materials
基金 国家科技重大专项(2013ZX06005006 2011ZX06004002)
关键词 压入模量 断裂伸长率 热-辐照联合 老化 核电厂 状态指标 indenter modulus elongation at break thermal-radiation ageing nuclear power plant state indicator
  • 相关文献

参考文献14

  • 1IEEE Std 323-1974, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations[S].
  • 2IEEE Std 383m-2003, IEEE Standard for Qualification Class 1E Electric Cables and Field Splices for Nuclear Power Generating Stations[S].
  • 3RCC-E-2012, Design and Construction Rules for Electrical Equipment of PWR Nuclear Islands[S].
  • 4NF M64-001-1991, Procedure for Qualification of Electric Equipment Installed in Containments for Pressurized Water Reactors Subject to Accident Conditions[S].
  • 5Wright D. Failure of Plastics and Rubber Products: Causes, Effects and Case Studies Involving Degradation[M]. 1st ed. La Vergne,TN USA:Lightning Source Inc,2001.
  • 6Sarathi R, Das S, Kumar C R A, et al. Analysis of Failure of Crosslinked Polyethylene Cables Because of Electrical Treeing: A Physicochemical Approach[J]. Journal of Applied Polymer Science,2004,92(4):2169-2178.
  • 7IEC/IEEE 62582-3-2012, Nuclear Power Plants-Instrumen- ta- tion and Control Important to Safety-Electrical Equipment Condition Monitoring Methods-Part 3:Elongation at Break[S].
  • 8GB/T2951.1l-2008,电缆和光缆绝缘和护套材料通用试验方法第11部分:通用试验方法-厚度和外形尺寸测量-机械性能试验[s].
  • 9U.S. Nuclear Regulatory Commission. NUREG/CR 7000, Es- sential Elements of an Electric Cable Condition Monitoring Program[R]. Washington DC USA:U.S.NRC,2010.
  • 10International Atomic Energy Agency. IAEA-TECDOC-1188, Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety: In-contain- ment Instrumentation and Control Cables[R]. Vienna,Austria: IAEA,2010.

二级参考文献5

  • 1刘韬,韩飞,施海宁,等.压缩模量监测技术在核电厂电缆老化评估中的应用[J].核动力运行和研究,2010,23(3):112-114.
  • 2Kim Jong-Seog. Evaluation of Nuclear Plant Cable Aging Through Condition Monitoring[J]. Journal of the Korean Nu- clear Society,2004,36(5):475-484.
  • 3Kim Jong-Seog. Evaluation of Cable Aging Degration Based on Plant Operaoing Cordition[J]. Journal of Nuclear Science and Technology,2005,42(8):745-753.
  • 4霍振星,杜伯学,王立,李华春.电力电缆在线诊断技术研究现状[J].绝缘材料,2008,41(3):66-68. 被引量:5
  • 5陈巧勇,文习山,王一,张云健.交联聚乙烯电缆在线绝缘检测的现状与发展[J].绝缘材料,2003,36(4):51-54. 被引量:7

共引文献3

同被引文献53

引证文献5

二级引证文献10

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部