期刊文献+

考虑蠕变作用的2.25Cr-1Mo-V钢加氢反应器设计方法 被引量:5

Design methods for hydrogenation reactors of 2.25Cr-1Mo-V considering creep
下载PDF
导出
摘要 以某台2.25Cr-1Mo-V钢加氢反应器为例,从工程角度介绍现行设计方法与ASME Code Case 2605-3在反应器设计中的应用,说明过去留有一定余量的设计是设备安全运行的原因之一。探讨了压力和温度载荷对蠕变参数的影响,其中压力对三轴度系数影响较大,而温度对蠕变松弛影响显著。最后提出在业主非强制要求进行完整分析的前提下,ASME Code Case 2605-3在工程上的简化应用。 By taking the hydrogenation reactor made of 2.25Cr-1Mo-V as an example,the application of current design method and the method in ASME Code Case 2605-3 in reactor design were introduced from perspective of engineering.It was explained that the design with a certain margin in the past is one of the reasons for the safe operation of the equipment.The influence of pressure and thermal load on creep parameters was discussed.Among them,pressure has a great influence on triaxiality coefficient,while temperature has a significant influence on creep relaxation.Finally,the simplified application of ASME Code Case 2605-3 in engineering was proposed under the premise of the owner′s noncompulsory requirement for integrity analysis.
作者 万里平 李宇 WAN Liping;LI Yu(Sinopec Engineering Incorporation,Beijing 100101,China)
出处 《压力容器》 北大核心 2021年第12期62-69,共8页 Pressure Vessel Technology
关键词 加氢反应器 2.25Cr-1Mo-V 蠕变疲劳 ASME Code Case 2605-3 hydrogenation reactor 2.25Cr-1Mo-V creep fatigue ASME Code Case 2605-3
  • 相关文献

参考文献10

二级参考文献82

  • 1杨宇峰,郭晓岚,刘金纯.Cr-Mo钢高温反应器的回火脆性及控制[J].当代化工,2005,34(1):64-66. 被引量:14
  • 2高亚萍.2.25Cr-1Mo-0.25V钢制板焊式加氢反应器的研制[J].压力容器,2006,23(12):33-36. 被引量:15
  • 3范志超,陈学东,陈凌,蒋家羚.1.25Cr0.5Mo钢疲劳蠕变及免于蠕变失效分析[J].浙江大学学报(工学版),2006,40(12):2021-2026. 被引量:3
  • 4余伟炜,高炳军.ANSYS在机械与化工装备中的应用[M].北京:中国水利水电出版社,2007.
  • 5GB150-2011,压力容器[S].
  • 6JB4732--1995,钢制压力容器--分析设计标准(2005年确认)[S].
  • 7SUSUMU T. Applications of Code Case 2605 for Fa- tigue Evaluation of Vessels Made in 2.25Cr - 1Mo - 0.25V Steels Slightly into Creep Range [ C]//PVP Conference. Washington : ASME ,2010.
  • 8ASME. ASME - MPC Symposium on Creep - Fatigue Interaction[ M ]. New York : ASME, 1976.
  • 9ASME Ⅲ - 1 2010,ASME Boiler and Pressure Vessel Code Section Ⅲ Division 1 Subsection NH [ S].
  • 10RCC - MR 2007, Design and Construction Rules for Mechanical Components of FBR Nuclear Islands and High Temperature Applications [ S ].

共引文献56

同被引文献48

引证文献5

二级引证文献4

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