国际热核试验堆第一壁材料的研究进展
Progress in Research of International Thermonuclear Experimental Reator First Wall Materials
摘 要
受控热核聚变能是未来最有希望的能源之一, 有效利用这种聚变能还有诸多技术难题, 其关键问题之一是国际热核试验堆第一壁材料的选用。综述了面向等离子体材料的性能及选择, 重点分析了铍、碳基材料、钨作为第一壁材料的研究进展与发展趋势。
聚变能
第一壁材料
钨
international thermonuclear experimental reator(ITER)
fusion energy
first wall material
tungsten
Abstract
Controlled thermonuclear fusion energy is one of the most promising energy sources in the future. To make use of the fusion energy, there are still many technical problems. One of the most critical issues is the selection of international thermonuclear experimental reator first wall materials. The performance and selection of plasma facing materials are reviewed, and focusing on the analysis of research progress and development trends of beryllium, carbon-based materials and tungsten as a first wall material.
中图分类号 TG146.1
所属栏目 综述
基金项目 国际热核聚变试验堆(ITER)计划专项资助项目(2010GB109004); 国家大学生创新项目(201210359013); 国家自然科学基金青年资助项目(51204064)
收稿日期 2012/9/12
修改稿日期 2013/6/16
网络出版日期
作者单位点击查看
备注丁孝禹(1990-), 男, 河南信阳人, 硕士研究生。
引用该论文: DING Xiao-yu,LI Hao,LUO Lai-ma,HUANG Li-mei,LUO Guang-nan,ZAN Xiang,ZHU Xiao-yong,WU Yu-cheng. Progress in Research of International Thermonuclear Experimental Reator First Wall Materials[J]. Materials for mechancial engineering, 2013, 37(11): 6～11
丁孝禹,李浩,罗来马,黄丽枚,罗广南,昝祥,朱晓勇,吴玉程. 国际热核试验堆第一壁材料的研究进展[J]. 机械工程材料, 2013, 37(11): 6～11
被引情况:
【1】陈泓谕,罗来马,谭晓月,李萍,吴玉程, "纤维增韧钨基复合材料的研究现状",机械工程材料 39, 10-15(2015)
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参考文献
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【23】张小锋, 刘维良, 郭双全, 等. 聚变堆中面向等离子体材料的研究进展[J].科技创新导报, 2010(3): 118-119.
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【32】WU C H, ALESSANDRINI C, MOORMANN R, et al. Evaluation of silicon doped CFCs for plasma facing material[J].Journal of Nuclear Materials, 1995, 220/222: 860-864.
【33】NODA N, PHILIPPS V, NEU R. A review of recent experiments on W and high Z materials as plasma-facing components in magnetic fusion devices[J].Journal of Nuclear Materials, 1997, 241/243: 227-243.
【34】DAVIS J W, BARABASH V R, MAKHANKOV A, et al. Assessment of tungsten for use in the ITER plasma facing components[J].Journal of Nuclear Materials, 1998, 258/263: 308-312.
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【37】朱玲旭, 郭双全, 张宇, 等.新型钨基面向等离子体材料的研究进展[J].材料导报, 2011(15): 42-45.
【38】刘凤, 李强, 罗广南, 等.超细晶/纳米晶钨—未来聚变堆面向等离子体材料[J].材料导报, 2011(19): 43-48.
【39】吴晓东, 傅小明, 戴起勋.用活性氧化钨制取微纳米钨和碳化钨粉末工艺研究[J].机械工程材料, 2005, 29(3): 52-54.
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【42】KURISHITA H, MATSUO S, ARAKAW H, et al. High temperature tensile properties and their application to toughness enhancement in ultra-fine grained W-(0-1.5)wt% TiC[J].Journal of Nuclear Materials, 2009, 386/388: 579-582.
【43】KURISHITA H, AMANO Y, KOBAYASHI S, et al. Development of ultra-fine grained W-TiC and their mechanical properties for fusion applications[J].Journal of Nuclear Materials, 2007, 367/370: 1453-1457.
【2】万元熙.磁约束核聚变研究现状和前景展望[J].现代物理知识, 1999, 11(5): 17-19.
【3】邱励俭.核聚变研究50年[J].核科学与工程, 2001, 21(1): 29-38.
【4】刘丹华, 谌继明, 吴继红, 等.国际热核实验堆第一壁材料CuCrZr合金及其与不锈钢焊接接头的力学性能[J].机械工程材料, 2009, 33(3): 46-49.
【5】陈勇, 吴玉程.面对等离子体钨基复合材料的制备及其性能研究[M].合肥: 合肥工业大学出版社, 2008: 1-164.
【6】TOMOAKI H. Japanese universities' activities for PFC development and PMI studies[J].Fusion Engineering and Design, 1998, 39/40: 439-444.
【7】朱士尧.核聚变原理[M].合肥: 中国科学技术大学出版社, 1992: 1-520.
【8】TANABE T, WADA M, OHGO T, et al. Applications of tungsten for plasma limiters in TEXTOR[J].Journal of Nuclear Materials, 2000, 283/287: 1128-1133.
【9】RUBEL M, TANABE T, PHILIPS V, et al. Graphite-tungsten twin limiters in studies of material mixing process on high heat flux components[J].Journal of Nuclear Materials, 2000, 283/287: 1089-1093.
【10】汪京荣.核聚变与国际热核聚变实验堆[J].稀有金属快报, 2002(10): 1-5.
【11】李云凯, 纪康俊.聚变堆等离子体面对材料[J].材料导报, 1999, 13(3): 3-5.
【12】SHIMADA M, COSTLEY A E, FEDERICI G, et al. Overview of goals and performance of ITER and strategy for plasma-wall interaction investigation[J].Journal of Nuclear Materials, 2005, 337/339: 808-815.
【13】BOLT H, BARABASH V, FEDERICI G, et al. Plasma facing and high heat flux materials-needs for ITER and beyond[J].Journal of Nuclear Materials, 2002, 307/311: 43-52.
【14】BOLT H, BARABASH V, KRAUSS W, et al. Materials for the plasma-facing components of fusion reactors[J].Journal of Nuclear Materials, 2004, 329/333: 66-73.
【15】吕广宏, 罗广南, 李建刚.磁约束核聚变托卡马克等离子体与壁相互作用研究进展[J].中国材料进展, 2010, 29(7): 42-48.
【16】许增裕.聚变材料研究的现状和展望[J].原子能科学技术, 2003, 37(增1): 105-110.
【17】BARABASH V, AKIBA M, MAZUL I, et al. Selection, development and characterization of plasma facing materials for ITER[J].Journal of Nuclear Materials, 1996, 233/237: 718-723.
【18】CONN R W, DOERNER R P, WON J. Beryllium as the plasma-facing material in fusion energy systems-experiments, evaluation, and comparison with alternative materials[J].Fusion Engineering and Design, 1997, 37(4): 481-513.
【19】PATEL B, PARSONS W. Operational beryllium handling experience at JET[J].Fusion Engineering and Design, 2003, 69(1/4): 689-694.
【20】DEKSNIS E B, PEACOCK A T, ALTMANN H, et al. Beryllium plasma-facing components: JET experience[J].Fusion Engineering and Design, 1997, 37(4): 515-530.
【21】BARABASH V, FEDERICE G, WU C H, et al. Material/plasma surface interaction issues following neutron damage[J].Journal of Nuclear Materials, 2003, 313/316: 42-51.
【22】钱蓉晖. 面对等离子体材料铍的抗热冲击性能[J].核材料与工程, 1999, 19(1): 57-60.
【23】张小锋, 刘维良, 郭双全, 等. 聚变堆中面向等离子体材料的研究进展[J].科技创新导报, 2010(3): 118-119.
【24】RAFFRAY A R, FDEDRICI G, BARABASH V, et al. Beryllium application in ITER plasma facing components[J].Fusion Engineering and Design, 1997, 37: 261-286.
【25】宋进仁, 翟更太, 刘朗.聚变装置用石墨材料的研究动向[J].新型碳材料, 1996, 11(3): 27-30.
【26】王明旭, 张年满, 王志文, 等.等离子体与石墨及其涂层相互作用的研究[J].核聚变与等离子体物理, 2000, 20(1): 31-36.
【27】王明旭, 许增裕, 谌继明, 等.HL-2A装置第一壁石墨组件研究[J].核聚变与等离子体物理, 2004, 24(1): 24-28.
【28】BARABASH V, AKIBA M, BONAL J P, et al. Carbon fiber composites application in ITER plasma facing components[J].Journal of Nuclear Materials, 1998, 258/263: 149-159.
【29】陈俊凌, 李建刚, 辜学茂, 等.HT-7U第一壁材料在HT-7 装置中的辐照实验研究[J].核聚变与等离子体物理, 2002, 22(2): 105-110.
【30】GUO Q G, LI J G, NODA N, et al. Selection of candidate doped graphite materials as plasma facing components for HT-7U device[J].Journal of Nuclear Materials, 2003, 313/316: 144-148.
【31】WU C H, ALESSANDRINI C, BONAL P, et al. Overview of EU CFCs development for plasma facing materials[J].Journal of Nuclear Materials, 1998, 258/263: 833-838.
【32】WU C H, ALESSANDRINI C, MOORMANN R, et al. Evaluation of silicon doped CFCs for plasma facing material[J].Journal of Nuclear Materials, 1995, 220/222: 860-864.
【33】NODA N, PHILIPPS V, NEU R. A review of recent experiments on W and high Z materials as plasma-facing components in magnetic fusion devices[J].Journal of Nuclear Materials, 1997, 241/243: 227-243.
【34】DAVIS J W, BARABASH V R, MAKHANKOV A, et al. Assessment of tungsten for use in the ITER plasma facing components[J].Journal of Nuclear Materials, 1998, 258/263: 308-312.
【35】SMID I, AKIBA M, VIEIDER G, et al. Development of tungsten armor and bonding to copper for plasma-interactive components[J].Journal of Nuclear Materials, 1998, 258/263: 160-172.
【36】ROEDIG M, KUEHNLEIN W, LINKE J, et al. Investigation of tungsten alloys as plasma facing materials for the ITER divertor[J].Fusion Engineering and Design, 2002, 61/62: 135-140.
【37】朱玲旭, 郭双全, 张宇, 等.新型钨基面向等离子体材料的研究进展[J].材料导报, 2011(15): 42-45.
【38】刘凤, 李强, 罗广南, 等.超细晶/纳米晶钨—未来聚变堆面向等离子体材料[J].材料导报, 2011(19): 43-48.
【39】吴晓东, 傅小明, 戴起勋.用活性氧化钨制取微纳米钨和碳化钨粉末工艺研究[J].机械工程材料, 2005, 29(3): 52-54.
【40】种法力, 陈勇, 吴玉程, 等.La2O3弥散增强钨合金面对等离子体材料及其高热负荷性能[J].材料科学与工程学报, 2009, 27(3): 415-417.
【41】ISHIJIMA Y, KURISHITA H, ARAKAWA H, et al. Microstructure and bend ductility of W-0.3 mass% TiC alloys fabricated by advanced powder-metallurgical processing[J].Materials Transactions, 2005, 46(3): 568-574.
【42】KURISHITA H, MATSUO S, ARAKAW H, et al. High temperature tensile properties and their application to toughness enhancement in ultra-fine grained W-(0-1.5)wt% TiC[J].Journal of Nuclear Materials, 2009, 386/388: 579-582.
【43】KURISHITA H, AMANO Y, KOBAYASHI S, et al. Development of ultra-fine grained W-TiC and their mechanical properties for fusion applications[J].Journal of Nuclear Materials, 2007, 367/370: 1453-1457.
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