期刊文献+

核电压力容器用厚钢板SA533B的组织及力学性能 被引量:14

Microstructure and mechanical properties of nuclear pressure vessel steel SA533B heavy plate
原文传递
导出
摘要 研究了核电压力容器用钢SA533B显微组织的变化对其力学性能的影响,尤其对韧性的影响。显微分析结果表明,该钢板的组织主要为粒状贝氏体及少量多边形铁素体。通过对调质态(QT)和模拟焊后热处理(SPWHT)态SA533B钢板的常规力学性能、不同温度的夏比冲击韧性(KCV)及断裂韧度(KJC)的深入研究,结果表明SA533B厚钢板经SPWHT升高了韧脆转变温度,降低了冲击韧性及断裂韧度,但SPWHT对常规力学性能无显著的影响。扫描电镜及电子探针分析仪分析表明,经模拟焊后热处理SA533B板材组织中的析出相有不同程度长大且有钼的析出,板材的韧性降低与微观组织中的析出相和钼的析出密切相关。 Microstructure and its effect on mechanical properties, especially toughness of a nuclear pressure vessel steel SA533B heavy plate were investigated. Granular bainite and some polygonal ferrite were identified in the steel by optical microscopy, scanning electron microscopy and transmission electron microscopy. Tensile properties at room temperature, Charpy impact values (KCV) and fracture toughness (gjc) were measured at different temperatures for the quenched-tempered (QT) and simulated post weld heat treatment (SPWHT) SA533B steel heavy plate, respectively. The results show that SPWHT increases the ductile-brittle transition temperature and decreases the gjc and KCV of the steel, however, no significant effects on its tensile properties are observed. The analysis of SEM and electron probe micro-analyzer (EPMA) shows that SPWHT coarsens the precipitation phases and promotes the precipitation of molybdenum precipitates. The decrease of toughness of the steel is related to the coarsening of precipitates and precipitation of molybdenum precititates.
出处 《材料热处理学报》 EI CAS CSCD 北大核心 2012年第8期84-88,共5页 Transactions of Materials and Heat Treatment
基金 宝山钢铁股份有限公司新产品项目(R07EBEJF40)
关键词 核电压力容器 粒状贝氏体 韧性 析出相 nuclear pressure vessel granular bainite toughness precipitation phase
  • 相关文献

参考文献10

  • 1Huang J Y, Hwang J R, Yeh J J, et al. Dynamic strain aging and grain size reduction effects on the fatigue resistance of SA533B steels[J]. Journal of Nuclear Materials, 2004,324(2 - 3 ) : 140 - 151.
  • 2Druce S G, Gage G, Jordan G. Effect of aging on properties of pressure vessel steels[J]. Acta Metallurgica, 1986, 34(4) : 641 -652.
  • 3李昌义,刘正东,林肇杰,金明.反应堆压力容器用钢的淬透性问题[J].材料热处理学报,2011,32(6):68-72. 被引量:21
  • 4Sterjovskia Z, Carr D G, Dunne D P, et al. Effect of PWHT cycles on fatigue crack growth and toughness of quenched and tempered pressure vessel steels[ J ]. Materials Science and Engineering A, 2005, 391 ( 1 - 2) : 256 - 263.
  • 5West Conshohocken. ASTM Standard E 1921-09c, Standard test method for determination of reference temperature, To , for ferritic steels in the transition range[S]. Philadelphia, SATM International, 2009.
  • 6Viehrig H W, Boehmert J, Dzugan J. Some issues by master curve concept [ J ]. Nuclear Engineering and Design, 2002, 212 ( 1 -3 ) : 115 - 124.
  • 7李云良,张汉谦,彭碧草,李金富.核电压力容器用钢的发展及研究现状[J].压力容器,2010,27(5):36-43. 被引量:32
  • 8Bowen P, Druce S G, Knott J F. Effects of mierostructure on cleavage fracture in pressure vessel steel[ J]. Acta Metallurgica, 1986, 34 (6) : 1121 -1131.
  • 9Kong Junhua, Zhen Lin, Guo Bin, et al. Influence of Mo content on microstructure and mechanical properties of high strength pipeline steel[ J ] Materials and Design, 2004, 25 (8) :723 - 728.
  • 10Lee W B, Hong S G, Park C G, et al. Influence of Mo on precipitation hardening in hot rolled HSLA steels containing Nb[ J]. Scripta Materialia 2000,43(3) : 319 -324.

二级参考文献38

  • 1王凤喜.核电站压力容器材料的发展[J].四川冶金,1993,15(2):40-45. 被引量:4
  • 2陈书贵.核电站反应堆压力容器用钢和制造工艺[J].大型铸锻件,1994(2):25-34. 被引量:14
  • 3杨自新,陈景毅.核反应堆压力容器用钢板(ASTM A533 BCI.1钢)的韧性[J].锅炉制造,1995(2):28-32. 被引量:5
  • 4国家发展和改革委员会.国家核电中长期规划(2005-2020年)[Z].北京,2006.3-4.
  • 5Druce S G,Edwards B C.Nuclear Energy[J].1980,19(5):347-360.
  • 6Faulkner R G,Song Shenhua,Flewitt P E J,et al.Grain Boundary Segregation under Neutron Irradiation in Dilute Alloys[J].Journal of Nuclear Materials,1998,255:189-209.
  • 7Dhooge A,Dolby R E,Sebille J,et al.A Review of Work Related to Reheat Cracking in Nuclear Reactor Pressure Vessel Steels[J].International Journal of Pressure Vessels and Piping,1978,(6):329-409.
  • 8Davies L M.A Comparison of Western and Eastern Nuclear Reactor Pressure Vessel Steels[J].International Journal of Pressure Vessels and Piping,1999,76:163-208.
  • 9Worrall G M,Buswell J T,English C A,et al.A Study of the Precipitation of Copper Particles in a Ferrite Matrix[J].Journal of Nuclear Materials,1987,148:107-114.
  • 10Miller M K,Pareige P,Burke M G.Understanding Pressure Vessel Steels:An Atom Probe Perspective[J].Materials Characterization,2000,44:235-254.

共引文献51

同被引文献99

引证文献14

二级引证文献54

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