聚变堆循环温度载荷下纯铜疲劳蠕变行为的数字相关测量
|
摘要
聚变堆偏滤器部件主要受到周期性高热流载荷的作用,其过渡纯铜夹层在高温变载荷下粘性效应突出,实际疲劳蠕变特性可能偏离常规的本构模型,开展相关研究是未来高热流偏滤器设计和评估的关键基础问题之一。本研究采用数字图像相关测量设备在新建成的聚变堆热疲劳综合实验平台上,测量了纯铜试件在拉应力条件下周期性循环热载荷对其疲劳蠕变特性的影响特征。结果表明温变载荷的温升速率上升会较大程度缩短纯铜稳态蠕变时间,提前进入快速蠕变阶段。
The divertor components of fusion reactor are mainly affected by periodic high heat flux(HHF) loading, and the viscous effect of transition pure copper interlayer is obvious under cyclic temperature variation loading, and the actual fatigue creep characteristics may deviate from the conventional constitutive model. To carry out related research is one of the key problems in the design and evaluation of high heat flux diverter in the future. In this study, the effect of cyclic temperature variation loading on fatigue creep characteristics of pure copper specimens under tensile stress were measured on the newly built thermal fatigue experimental platform of fusion reactor with digital image correlation(DIC) measurement equipment. Results show that the temperature rise rate in temperature variation loading will shorten the steady state creep time of pure copper to a large extent and advance to the rapid creep stage. This result will have an important effect on the fatigue life evaluation of pure copper interlayer in fusion reactor divertor considering transient thermal load.
The divertor components of fusion reactor are mainly affected by periodic high heat flux(HHF) loading, and the viscous effect of transition pure copper interlayer is obvious under cyclic temperature variation loading, and the actual fatigue creep characteristics may deviate from the conventional constitutive model. To carry out related research is one of the key problems in the design and evaluation of high heat flux diverter in the future. In this study, the effect of cyclic temperature variation loading on fatigue creep characteristics of pure copper specimens under tensile stress were measured on the newly built thermal fatigue experimental platform of fusion reactor with digital image correlation(DIC) measurement equipment. Results show that the temperature rise rate in temperature variation loading will shorten the steady state creep time of pure copper to a large extent and advance to the rapid creep stage. This result will have an important effect on the fatigue life evaluation of pure copper interlayer in fusion reactor divertor considering transient thermal load.
引文
[1] Arnoux G,Bazylev B,Lehnen M,et al.Heat load measurements on the JET first wall during disruptions[J].Journal of Nuclear Materials,2011,415(1):S817-S820.
[2] Lehnen M,Arnoux G,Hartmann N,et al.Disruption heat loads and their mitigation in JET with the ITER-like wall[J].Journal of Nuclear Materials,2013,438:S102-S107.
[3] Linke J,Akiba M,Bolt H.Performance of beryllium,carbon,and tungsten under intense thermal fluxes[J].Journal of Nuclear Materials,1997,241:1210-1216.
[4] Li Q,HE X.Surface damage of tungsten during plasma disruption[J].Journal of Hefei University of Technology (Natural Science),2008,10:1181-1183.
[5] Wirtz M,Linke J,Pintsuk G.Thermal shock behaviour of tungsten after high flux H-plasma loading[J].Journal of Nuclear Materials,2013,443(1):497-501.
[6] Sun Zhaoxuan,Li Qiang,Wang Wanjing,et al.Post examination of tungsten monoblocks subjected to high heat flux tests of ITER full-tungsten divertor qualification program[J].Fusion Engineering and Design,2017,121:60-69.
[7] Leedy K D,Stubbins J F,Singh B N,et al.Fatigue behavior of copper and selected copper alloys for high heat flux applications[J].Journal of Nuclear Materials,1996,233:547-552.
[8] Singh B N,Stubbins J F,Toft P.The infuence of neutron irradiation on the fatigue performance of OFHC copper and a dispersion strengthened copper alloy[J].Journal of Nuclear Materials,1999,275:125-137.
[9] Li G,Thomas B G,Stubbins J F.Modeling creep and fatigue of copper alloys[J].Metallurgical & Materials Transactions A,2000,31(10):2491-2502.
[10] Li Meimei,Singh B N,Stubbins J F.Room temperature creep-fatigue response of selected copper alloys for high heat flux applications[J].Journal of Nuclear Materials,2004,329:865-869.
[11] Li M Y,Werner E,You J H.Low cycle fatigue behavior of ITER-like divertor target under DEMO-relevant operation conditions[J].Fusion Engineering and Design,2015,90:88-96.
[12] 潘兵,谢惠民,李艳杰.用于物体表面形貌和变形测量的三维数字图像相关方法[J].实验力学,2007,22(6):556-567 (PAN Bing,XIE Huimin,LI Yanjie.Three-dimensional digital image correlation method for shape and deformation measurement of an object surface[J].Journal of Experimental Mechanics,2007,22(6):556-567 (in Chinese))
[13] Michael Kassner.Fundamentals of creep in metals and alloys[M].Elsevier Science,2009.
[14] Qian Y,Peng X B,Wang L,et al.Evaluation of performance for the EAST upgraded divertor targets during type I ELMy H-mode[J].Nuclear Fusion,2016,56:026010.
[2] Lehnen M,Arnoux G,Hartmann N,et al.Disruption heat loads and their mitigation in JET with the ITER-like wall[J].Journal of Nuclear Materials,2013,438:S102-S107.
[3] Linke J,Akiba M,Bolt H.Performance of beryllium,carbon,and tungsten under intense thermal fluxes[J].Journal of Nuclear Materials,1997,241:1210-1216.
[4] Li Q,HE X.Surface damage of tungsten during plasma disruption[J].Journal of Hefei University of Technology (Natural Science),2008,10:1181-1183.
[5] Wirtz M,Linke J,Pintsuk G.Thermal shock behaviour of tungsten after high flux H-plasma loading[J].Journal of Nuclear Materials,2013,443(1):497-501.
[6] Sun Zhaoxuan,Li Qiang,Wang Wanjing,et al.Post examination of tungsten monoblocks subjected to high heat flux tests of ITER full-tungsten divertor qualification program[J].Fusion Engineering and Design,2017,121:60-69.
[7] Leedy K D,Stubbins J F,Singh B N,et al.Fatigue behavior of copper and selected copper alloys for high heat flux applications[J].Journal of Nuclear Materials,1996,233:547-552.
[8] Singh B N,Stubbins J F,Toft P.The infuence of neutron irradiation on the fatigue performance of OFHC copper and a dispersion strengthened copper alloy[J].Journal of Nuclear Materials,1999,275:125-137.
[9] Li G,Thomas B G,Stubbins J F.Modeling creep and fatigue of copper alloys[J].Metallurgical & Materials Transactions A,2000,31(10):2491-2502.
[10] Li Meimei,Singh B N,Stubbins J F.Room temperature creep-fatigue response of selected copper alloys for high heat flux applications[J].Journal of Nuclear Materials,2004,329:865-869.
[11] Li M Y,Werner E,You J H.Low cycle fatigue behavior of ITER-like divertor target under DEMO-relevant operation conditions[J].Fusion Engineering and Design,2015,90:88-96.
[12] 潘兵,谢惠民,李艳杰.用于物体表面形貌和变形测量的三维数字图像相关方法[J].实验力学,2007,22(6):556-567 (PAN Bing,XIE Huimin,LI Yanjie.Three-dimensional digital image correlation method for shape and deformation measurement of an object surface[J].Journal of Experimental Mechanics,2007,22(6):556-567 (in Chinese))
[13] Michael Kassner.Fundamentals of creep in metals and alloys[M].Elsevier Science,2009.
[14] Qian Y,Peng X B,Wang L,et al.Evaluation of performance for the EAST upgraded divertor targets during type I ELMy H-mode[J].Nuclear Fusion,2016,56:026010.