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430℃下2.98dpa中子辐照后CLAM钢的拉伸和冲击性能 被引量:2

Tensile and Impact Properties of CLAM Steel after Neutron Irradiation to 2.98dpa at 430 ℃
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摘要 利用高通量工程试验堆HFETR开展了CLAM钢430℃下2.98dpa的中子辐照实验,通过辐照前后拉伸和冲击性能测试与对比分析,研究了CLAM钢的中子辐照硬化和脆化效应。结果显示,CLAM钢辐照后室温测试的抗拉强度和屈服强度分别为710 MPa和615 MPa,较辐照前分别下降16 MPa和-0.5MPa,总延伸率减小1%,断面收缩率下降4%,保持良好的强度、塑性和韧性。冲击测试表明,CLAM钢辐照前后韧脆转变温度基本相同,上平台能量无明显变化,约为217J,未出现明显辐照脆化。CLAM钢的抗辐照性能略优于其他低活化铁素体/马氏体RAFM钢在类似辐照条件下的性能。 The neutron irradiation experiments for China Low Activation Martensitic(CLAM)steels were carried out in High Flux Engineering Test Reactor(HFETR),the effects of neutron irradiation on the hardening and embrittlement behavior of CLAM steels were investigated before and after neutron irradiation to 2.98 dpa at 430 ℃.The results showed that ultimate strength and yield stress of CLAM steel tested at room temperature are 710 MPa and 615 MPa,which decreased about 16 MPa and-0.5MPa as compared with the unirradiated samples,respectively.And its Ductile to Brittle Transition Temperature(DBTT)shift was no obvious shift.While the upper shelf energy after irradiation was 217 J,which almost the same with that of unirradiated samples.The irradiation resistant of CLAM steel are slightly better than that of other Reduced Activation Ferritic/Martensitic(RAFM)steels under similar irradiation conditions.
作者 信敬平 刘少军 李春京 徐刚 黄群英 吴宜灿 XIN Jing-ping LIU Shao-jun LI Chun-jing XU Gang HUANG Qun-ying WU Yi-can(Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China)
出处 《核科学与工程》 CAS CSCD 北大核心 2016年第4期487-491,共5页 Nuclear Science and Engineering
基金 国际热核聚变实验堆ITER计划国内配套专项项目(2013GB108005 2014GB112003) 中国科学院战略性先导科技专项(XDA03040000) 中国科学院知识创新工程重要方向项目(KJCX2-YW-N35)
关键词 CLAM钢 中子辐照 拉伸 冲击 CLAM steel Neutron irradiation Tensile Impact
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  • 1吴宜灿,柯严,郑善良,汪卫华,储德林,黄群英,刘晓平,许德政,王红艳,黄德所,朱晓翔,高纯静,李静惊,陈义学,吴斌,汪太平,柏云清,章毛连,刘松林,罗月童,刘萍,李春京,李强,童莉莉,翁晓毅,吴磊,王祥科,FDS课题组.聚变驱动次临界堆概念设计研究[J].核科学与工程,2004,24(1):72-80. 被引量:53
  • 2[22]CARDELLA A,RIGAL E,BEDEL L,et al.The manufacturing technologies of the European breeding blankets[J].J Nucl Mater,2004,329-333:133-140. 被引量:1
  • 3[23]NORAJITRA P,REIMANN G,RUPRECHT R,et al.HIP experiments on the first wall and cooling plate specimens for the EU HCPB blanket[J].J Nucl Mater,2002,307-311:1 558-1 562. 被引量:1
  • 4[24]RIGAL E,BRIOTTET L,DELLIS C,et al.HIP diffusion bonding and forming of martensitic steel for ITER test blanket modules[C]// Proceeding of the 21st Symposium on Fusion Technology.[S.1.]:[s.n.],2000:1 223-1 226. 被引量:1
  • 5[26]LI C,HUANG Q,ZHANG P,et al.Preliminary experimental study on hot isostatic pressing diffusion bonding for CLAM/CLAM[J].Fusion Eng Des,2007,82:2 627-2 633. 被引量:1
  • 6[27]HUANG Q,LI Y,WU Y,et al.Status and strategy of fusion materials development in China:Report of 13th International Conference on Fusion Reactor Materials (ICFRM-13)[R].Nice,France:[s.n.],2007. 被引量:1
  • 7[28]SMITH D L,KONYS J,MUROGA T,et al.Development of coatings for fusion power applications[J].J Nucl Mater,2002,307-311:1 314-1 322. 被引量:1
  • 8[29]LI X,GANG Y,YU J,et al.AI based coating on martensitic steel[J].J Nucl Mater,2004,329-333:1 407-1 410. 被引量:1
  • 9[30]YOUNGBLOOD G E,KURTZ R J,JONES R H.SiCk/SiC design for a flow channel insert,DE-AC06-76RLO-1830[R/OL].http://www.osti.gov/bridge/servlets/pur1/911784-2vhvSQ/,2007. 被引量:1
  • 10[31]BROC M,FAUVET P,FLAMENT T,et al.Compatibility of 316L stainless steel with liquid and solid tritium breeding materials[J].J Nucl Mater,1986,141-143:611-616. 被引量:1

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