中国ITER计划采购包进展
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摘要
国际热核聚变实验堆(ITER)计划,是我国以平等、全权伙伴身份参加的迄今为止规模最大的国际科技合作项目.它的实施结果将决定人类能否迅速地、大规模地使用资源丰富且无污染的聚变能,并从根本上解决未来能源问题.本文简要介绍了中国参与ITER计划的主要背景和总体情况,并概述了中国ITER采购包的执行成果,展示了中国的聚变实力,并为中国聚变工程实验堆(CFETR)奠定了丰富的科学与技术基础.
International Thermonuclear Experimental Reactor(ITER) is one of the largest and the most influential international scientific and technological cooperation projects in the world. China is participating in ITER project as an equal partner.The successful implementation of ITER project would probably ensure that human kind rapidly and widely utilizes the fusion energy without pollution emission, thus permanently solving the energy problem. In this paper, the progress of ITER Implementation in China is introduced. Its rapid progress indicates that China has already taken the lead position towards the manufacture of ITER components, and pushes the scientific and technological development forward in fusion energy research field. On the other hand, the rich experience resulted from ITER project will be of benefit in our next DEMO: China Fusion Engineering Experimental Reactor(CFETR).
International Thermonuclear Experimental Reactor(ITER) is one of the largest and the most influential international scientific and technological cooperation projects in the world. China is participating in ITER project as an equal partner.The successful implementation of ITER project would probably ensure that human kind rapidly and widely utilizes the fusion energy without pollution emission, thus permanently solving the energy problem. In this paper, the progress of ITER Implementation in China is introduced. Its rapid progress indicates that China has already taken the lead position towards the manufacture of ITER components, and pushes the scientific and technological development forward in fusion energy research field. On the other hand, the rich experience resulted from ITER project will be of benefit in our next DEMO: China Fusion Engineering Experimental Reactor(CFETR).
引文
1 Feng K M,Controlled nuclear fusion and ITER project.China Nuclear Power,2009,2:212-219
2 Pan C H.The International Thermonuclear Experimental Reactor and the future of nuclear fusion energy(in Chinese).Physics,2010,39:375-378[潘传红.国际热核实验反应堆(ITER)计划与未来核聚变能源.物理,2010,39:375-378]
3 Wan Y X.Current status and prospect of magnetic confinement fusion research(in Chinese).Modern Phys,1999,11:17-19[万元熙.磁约束核聚变研究现状和前景展望.现代物理知识,1999,11:17-19]
4 Pan Y,Zhuang G,Zhang M,et al.The ITER program and its impact on China’s nuclear energy development(in Chinese).Physics,2010,39:379-384[潘垣,庄革,张明,等.国际热核实验反应堆计划及其对中国核能发展战略的影响.物理,2010,39:379-384]
5 Li J G.Present status and development of superconducting Tokamak research in China(in Chinese).Bull Chin Acad Sci,2007,22:404-410[李建刚.我国超导托卡马克的现状及发展.中国科学院院刊,2007,2:404-410]
6 Li J G.The status and progress of tokamak research(in Chinese).Physics,2016,45:88-97[李建刚.托卡马克研究的现状及发展.物理,2016,45:88-97]
7 Luo D L,He K H.International Thermonuclear Experimental Reactor-from initiative to implementation(in Chinese).Chin Basic Sci,2008,2:3-8[罗德隆,何开辉.国际热核聚变实验堆计划--从倡议到实施.中国基础科学,2008,2:3-8]
8 Pan Y,Zhuang G,Zhang M,et al.The ITER program and its impact on China’s nuclear energy development.Physics,2010,39:379-384
9 Li H.ITER decade:Contribute Chinese wisdom to artificial sun(in Chinese).China Scitech Busi,2018,1:37-40[李浩.ITER十年:为“人造太阳”贡献中国智慧.科技中国,2018,1:37-40]
10 Wu Y,Qin J G,Liu B,et al.Status of the ITER conductors in China.IEEE Trans Appl Supercond,2016,26:1-5
11 Qin J G,Wu Y,Liu B,et al.Manufacturing of ITER PF5 and CC sample conductors.IEEE Trans Appl Supercond,2014,24:62-66
12 Qin J,Dai C,Liao G,et al.Tensile test of SS 316LN jacket with different conditions.Cryogenics,2014,64:16-20
13 Peng J Q,Wu H P,Wu Y,et al.Numerical simulation on the rollers’temperature of ITER PF compaction machine(in Chinese).Cryo Supercond,2011,39:1-6[彭晋卿,吴会平,武玉,等.ITER PF导体缩径机轧辊温升数值模拟研究.低温与超导,2011,39:1-6]
14 Liu X C,Wu Y,Liu H J.Reentrant test for ITER PF butt welds(in Chinese).Nondestruct Testing,2014,36:69-71[刘小川,武玉,刘华军.ITER超导导体铠甲焊缝的渗透检测.无损检测,2014,36:69-71]
15 Yu Z Z,Wu Y,Xia Y S,et al.Synchronous speed control for conductor twisting system of ITER(in Chinese).J Hefei Univ Tech(Nat Sci),2011,34:709-711[余中正,武玉,夏永胜,等.ITER导体收缆系统速度同步控制方案分析.合肥工业大学学报(自然科学版),2011,34:709-711]
16 Wu Y,Han Q Y,Lin F,et al.Study on fabrication of ITER TF conductor(in Chinese).Cryo Supercond,2009,37:33-37[武玉,韩奇阳,凌峰,等.TERTF导体制造研究.超导技术,2009,37:33-37]
17 Fu P.Introduction of power supply system for International Fusion Reactor ITER(in Chinese).Power Electron,2014,48:1-7[傅鹏.国际聚变堆装置电源系统综述.电力电子技术,2014,48:1-7]
18 Fu P,Gao G,Xu L W,et al.Review and analysis of the AC/DC converter of ITER coil power supply.In:Proceedings of the Twenty-Fifth Annual IEEE Applied Power Electronics Conference and Exposition.Palm:Springs,2010.1810-1816
19 Fu P,Gao G,Song Z H Q,et al.Preliminary design of the poloidal field AC/DC converter system for the ITER coil power supply.Fusion Sci Tech,2013,64:741-747
20 Tao J,Benfatto I,Goff J K,et al.ITER coil power supply and distribution system.In:Proceedings of the IEEE/NPSS 24th Symposiun on Fusion Engineering.Chicago,2011.1-8
21 Wu W S,Song Z Q,Fu P.Short circuit fault analysis of ITER poloidal field converter power supply(in Chinese).Chin J Power Sources,2014,38:337-340[吴万松,宋执权,傅鹏.ITER极向场变流器电源短路故障分析.电源技术,2014,38:337-340]
22 Yang Z G,Fu P,Huang Y Y,et al.Study and implementation of primary system for ITER pulsed power electrical network(in Chinese).High Power Laser Particle Beams,2017,29:065009[杨志刚,傅鹏,黄懿赟,等.ITER脉冲功率变电站一次系统研究与实现.强激光与粒子束,2017,29:065009]
23 Bi Y F,Ding K Z,Cheng A Y,et al.R&D on a 68 kA HTS current lead for ITER project(in Chinese).Chin J Low Temper Phys,2009,31:41-45[毕延芳,丁开忠,成安义,等.ITER68 kA高温超导特大电流引线研发.低温物理学报,2009,31:41-45]
24 Lin X J,Bi Y F,Ding K Z,et al.R&D on shunt for high safety hts current leads for ITER(in Chinese).Chin J Low Temper Phys,2009,31:171-174[林贤军,毕延芳,丁开忠,等.ITER高温超导电流引线的高安全分流器研究.低温物理学报,2009,31:171-174]
25 Foussat A,Libeyre P,Mitchell N,et al.Overview of the ITER correction coils design.IEEE Trans Appl Supercond,2010,20:402-406
26 Foussat A,Dolgetta N,Jong C,et al.From design to development phase of the ITER correction coils.IEEE Trans Appl Supercond,2011,21:1960-1963
27 Libeyre P,Cormany C,Dolgetta N,et al.Qualification of the manufacturing procedures of the ITER correction coils.IEEE Trans Appl Supercond,2017,27:1-5
28 Jin C S,Hu Q S,Xu T J,et al.Structural analysis and optimization for equatorial diagnostic port plug of ITER(in Chinese).Vacuum,2011,48:68-71[金传山,胡庆生,许铁军,等.ITER水平诊断窗口插件结构分析及优化.真空,2011,48:68-71]
29 Zhang S,Ge J,Zhang B,et al.Cooling circle design and testing for ITER radial X-ray camera.Fusion Eng Des,2017,125:77-84
30 Hu L,Chen K,Chen Y,et al.Preliminary design and R&D of ITER diagnostic-radial X-ray camera.Nucl Instrum Methods Phys Res Sect A,2017,870:50-54
31 Liu Y.Overview of ITER procurement and fusion research progress in SWIP(in Chinese).In:Proceedings of the 10th Anniversary of the ITER.Beijing,2017[刘永.核西物院ITER计划执行和核聚变研究进展.见:ITER十年学术报告论文集.北京,2017]
32 Wang P,Chen J,Li Q,et al.Study on the microstructure and properties evolution of CuCrZr/316LN-IG explosion bonding for ITER first wall components.Fusion Eng Des,2017,124:1135-1139
33 Chen J M,Wang Pi H,Jin F Y,et al.The first wall material of ITER(in Chinese).In:Proceedings of the 10th Anniversary of the ITER.Beijing,2017[谌继明,王平怀,金凡亚,等.国际热核聚变实验堆第一壁材料.见:ITER十年学术报告论文集.北京,2017]
34 Kang W S,Chen J M,Wu J H,et al.Design and key manufacturing technologies R&D of full scale prototype for ITER blanket shield block(in Chinese).Nucl Fusion Plasma Phys,2015,35:35-40[康伟山,谌继明,吴继红,等.ITER包层屏蔽块全尺寸原型件的设计与关键制造技术的研发.核聚变与等离子体物理,2015,35:35-40]
35 Xu W Y,Li P Y,Wei H H,et al.Cooling pipe system of ITER’s poloidal field coil support(in Chinese).Nucl Fusion Plasma Phys,2018,38:69-73[许婉韵,李鹏远,魏海鸿,等.ITER极向场磁体支撑冷却系统设计、分析与优化.核聚变与等离子体物理,2018,38:69-73]
36 Xu J,Wen W,Chen J,et al.ITER PF6 winding line multi-axis automatic controlling system.Fusion Eng Des,2017,121:124-129
37 Du S,Wen W,Chen J,et al.ITER PF6 double pancakes winding line.Fusion Eng Des,2017,116:10-16
38 Du S,Wen W,Shen G,et al.Qualification of ITER PF6 helium inlet.Fusion Eng Des,2018,134:1-4
39 Pan C H.Key technology R&D activities and Test of ITER procurement in China(in Chinese).In:Proceedings of the 10th Anniversary of the ITER.Beijing,2017[潘传红.ITER采购包关键技术预研和测试总体情况报告.见:ITER十年学术报告论文集.北京,2017]
2 Pan C H.The International Thermonuclear Experimental Reactor and the future of nuclear fusion energy(in Chinese).Physics,2010,39:375-378[潘传红.国际热核实验反应堆(ITER)计划与未来核聚变能源.物理,2010,39:375-378]
3 Wan Y X.Current status and prospect of magnetic confinement fusion research(in Chinese).Modern Phys,1999,11:17-19[万元熙.磁约束核聚变研究现状和前景展望.现代物理知识,1999,11:17-19]
4 Pan Y,Zhuang G,Zhang M,et al.The ITER program and its impact on China’s nuclear energy development(in Chinese).Physics,2010,39:379-384[潘垣,庄革,张明,等.国际热核实验反应堆计划及其对中国核能发展战略的影响.物理,2010,39:379-384]
5 Li J G.Present status and development of superconducting Tokamak research in China(in Chinese).Bull Chin Acad Sci,2007,22:404-410[李建刚.我国超导托卡马克的现状及发展.中国科学院院刊,2007,2:404-410]
6 Li J G.The status and progress of tokamak research(in Chinese).Physics,2016,45:88-97[李建刚.托卡马克研究的现状及发展.物理,2016,45:88-97]
7 Luo D L,He K H.International Thermonuclear Experimental Reactor-from initiative to implementation(in Chinese).Chin Basic Sci,2008,2:3-8[罗德隆,何开辉.国际热核聚变实验堆计划--从倡议到实施.中国基础科学,2008,2:3-8]
8 Pan Y,Zhuang G,Zhang M,et al.The ITER program and its impact on China’s nuclear energy development.Physics,2010,39:379-384
9 Li H.ITER decade:Contribute Chinese wisdom to artificial sun(in Chinese).China Scitech Busi,2018,1:37-40[李浩.ITER十年:为“人造太阳”贡献中国智慧.科技中国,2018,1:37-40]
10 Wu Y,Qin J G,Liu B,et al.Status of the ITER conductors in China.IEEE Trans Appl Supercond,2016,26:1-5
11 Qin J G,Wu Y,Liu B,et al.Manufacturing of ITER PF5 and CC sample conductors.IEEE Trans Appl Supercond,2014,24:62-66
12 Qin J,Dai C,Liao G,et al.Tensile test of SS 316LN jacket with different conditions.Cryogenics,2014,64:16-20
13 Peng J Q,Wu H P,Wu Y,et al.Numerical simulation on the rollers’temperature of ITER PF compaction machine(in Chinese).Cryo Supercond,2011,39:1-6[彭晋卿,吴会平,武玉,等.ITER PF导体缩径机轧辊温升数值模拟研究.低温与超导,2011,39:1-6]
14 Liu X C,Wu Y,Liu H J.Reentrant test for ITER PF butt welds(in Chinese).Nondestruct Testing,2014,36:69-71[刘小川,武玉,刘华军.ITER超导导体铠甲焊缝的渗透检测.无损检测,2014,36:69-71]
15 Yu Z Z,Wu Y,Xia Y S,et al.Synchronous speed control for conductor twisting system of ITER(in Chinese).J Hefei Univ Tech(Nat Sci),2011,34:709-711[余中正,武玉,夏永胜,等.ITER导体收缆系统速度同步控制方案分析.合肥工业大学学报(自然科学版),2011,34:709-711]
16 Wu Y,Han Q Y,Lin F,et al.Study on fabrication of ITER TF conductor(in Chinese).Cryo Supercond,2009,37:33-37[武玉,韩奇阳,凌峰,等.TERTF导体制造研究.超导技术,2009,37:33-37]
17 Fu P.Introduction of power supply system for International Fusion Reactor ITER(in Chinese).Power Electron,2014,48:1-7[傅鹏.国际聚变堆装置电源系统综述.电力电子技术,2014,48:1-7]
18 Fu P,Gao G,Xu L W,et al.Review and analysis of the AC/DC converter of ITER coil power supply.In:Proceedings of the Twenty-Fifth Annual IEEE Applied Power Electronics Conference and Exposition.Palm:Springs,2010.1810-1816
19 Fu P,Gao G,Song Z H Q,et al.Preliminary design of the poloidal field AC/DC converter system for the ITER coil power supply.Fusion Sci Tech,2013,64:741-747
20 Tao J,Benfatto I,Goff J K,et al.ITER coil power supply and distribution system.In:Proceedings of the IEEE/NPSS 24th Symposiun on Fusion Engineering.Chicago,2011.1-8
21 Wu W S,Song Z Q,Fu P.Short circuit fault analysis of ITER poloidal field converter power supply(in Chinese).Chin J Power Sources,2014,38:337-340[吴万松,宋执权,傅鹏.ITER极向场变流器电源短路故障分析.电源技术,2014,38:337-340]
22 Yang Z G,Fu P,Huang Y Y,et al.Study and implementation of primary system for ITER pulsed power electrical network(in Chinese).High Power Laser Particle Beams,2017,29:065009[杨志刚,傅鹏,黄懿赟,等.ITER脉冲功率变电站一次系统研究与实现.强激光与粒子束,2017,29:065009]
23 Bi Y F,Ding K Z,Cheng A Y,et al.R&D on a 68 kA HTS current lead for ITER project(in Chinese).Chin J Low Temper Phys,2009,31:41-45[毕延芳,丁开忠,成安义,等.ITER68 kA高温超导特大电流引线研发.低温物理学报,2009,31:41-45]
24 Lin X J,Bi Y F,Ding K Z,et al.R&D on shunt for high safety hts current leads for ITER(in Chinese).Chin J Low Temper Phys,2009,31:171-174[林贤军,毕延芳,丁开忠,等.ITER高温超导电流引线的高安全分流器研究.低温物理学报,2009,31:171-174]
25 Foussat A,Libeyre P,Mitchell N,et al.Overview of the ITER correction coils design.IEEE Trans Appl Supercond,2010,20:402-406
26 Foussat A,Dolgetta N,Jong C,et al.From design to development phase of the ITER correction coils.IEEE Trans Appl Supercond,2011,21:1960-1963
27 Libeyre P,Cormany C,Dolgetta N,et al.Qualification of the manufacturing procedures of the ITER correction coils.IEEE Trans Appl Supercond,2017,27:1-5
28 Jin C S,Hu Q S,Xu T J,et al.Structural analysis and optimization for equatorial diagnostic port plug of ITER(in Chinese).Vacuum,2011,48:68-71[金传山,胡庆生,许铁军,等.ITER水平诊断窗口插件结构分析及优化.真空,2011,48:68-71]
29 Zhang S,Ge J,Zhang B,et al.Cooling circle design and testing for ITER radial X-ray camera.Fusion Eng Des,2017,125:77-84
30 Hu L,Chen K,Chen Y,et al.Preliminary design and R&D of ITER diagnostic-radial X-ray camera.Nucl Instrum Methods Phys Res Sect A,2017,870:50-54
31 Liu Y.Overview of ITER procurement and fusion research progress in SWIP(in Chinese).In:Proceedings of the 10th Anniversary of the ITER.Beijing,2017[刘永.核西物院ITER计划执行和核聚变研究进展.见:ITER十年学术报告论文集.北京,2017]
32 Wang P,Chen J,Li Q,et al.Study on the microstructure and properties evolution of CuCrZr/316LN-IG explosion bonding for ITER first wall components.Fusion Eng Des,2017,124:1135-1139
33 Chen J M,Wang Pi H,Jin F Y,et al.The first wall material of ITER(in Chinese).In:Proceedings of the 10th Anniversary of the ITER.Beijing,2017[谌继明,王平怀,金凡亚,等.国际热核聚变实验堆第一壁材料.见:ITER十年学术报告论文集.北京,2017]
34 Kang W S,Chen J M,Wu J H,et al.Design and key manufacturing technologies R&D of full scale prototype for ITER blanket shield block(in Chinese).Nucl Fusion Plasma Phys,2015,35:35-40[康伟山,谌继明,吴继红,等.ITER包层屏蔽块全尺寸原型件的设计与关键制造技术的研发.核聚变与等离子体物理,2015,35:35-40]
35 Xu W Y,Li P Y,Wei H H,et al.Cooling pipe system of ITER’s poloidal field coil support(in Chinese).Nucl Fusion Plasma Phys,2018,38:69-73[许婉韵,李鹏远,魏海鸿,等.ITER极向场磁体支撑冷却系统设计、分析与优化.核聚变与等离子体物理,2018,38:69-73]
36 Xu J,Wen W,Chen J,et al.ITER PF6 winding line multi-axis automatic controlling system.Fusion Eng Des,2017,121:124-129
37 Du S,Wen W,Chen J,et al.ITER PF6 double pancakes winding line.Fusion Eng Des,2017,116:10-16
38 Du S,Wen W,Shen G,et al.Qualification of ITER PF6 helium inlet.Fusion Eng Des,2018,134:1-4
39 Pan C H.Key technology R&D activities and Test of ITER procurement in China(in Chinese).In:Proceedings of the 10th Anniversary of the ITER.Beijing,2017[潘传红.ITER采购包关键技术预研和测试总体情况报告.见:ITER十年学术报告论文集.北京,2017]