氘氘聚变中子源大口径强磁场磁压缩磁体的设计与优化

doi:10.12096/j.2096-4528.pgt.24173

发电技术 ›› 2024, Vol. 45 ›› Issue (6): 1016-1022.DOI: 10.12096/j.2096-4528.pgt.24173

• 可控核聚变及其发电技术 •

氘氘聚变中子源大口径强磁场磁压缩磁体的设计与优化

周渝深¹^,², 潘垣¹^,², 李传¹^,², 饶波¹^,², 杨勇¹^,²

^1.强电磁技术全国重点实验室(华中科技大学电气与电子工程学院)，湖北省武汉市 430074
^2.磁约束聚变与等离子体国际合作联合实验室(华中科技大学电气与电子工程学院)，湖北省 ;武汉市 430074

收稿日期:2024-08-01 修回日期:2024-10-25 出版日期:2024-12-31 发布日期:2024-12-30
通讯作者: 李传
作者简介:周渝深(2000)，男，硕士研究生，研究方向为大口径强磁场磁体的多物理场耦合的有限元分析与建造测试，870039748@qq.com；
潘垣(1933)，男，教授，中国工程院院士，研究方向为超导电力、脉冲功率技术、等离子体物理与核聚变技术；
李传(1989)，男，博士，副教授，研究方向为带电粒子诱导水汽成核及生长机理研究、气体放电数值模拟、静电集雾/消雾技术研究、磁体线圈和高功率大电流电抗器的研制与优化，本文通信作者，lichuan@hust.edu.cn；
饶波(1986)，男，博士，副教授，研究方向为磁约束聚变应用中的电磁装置设计及相关等离子体控制，聚变新途径、新方法；
杨勇(1989)，男，博士，讲师，研究方向为聚变磁体电源、电磁分析与设计。
基金资助:
国家重点研发计划项目(2022YFE03150102);国家自然科学基金项目(52207158);华中科技大学“交叉研究支持计划”(2024JCYJ017)

Design and Optimization of Deuterium-Deuterium Fusion Neutron Source Large-Size and High Magnetic Field Magnetic Compression Magnet

Yushen ZHOU¹^,², Yuan PAN¹^,², Chuan LI¹^,², Bo RAO¹^,², Yong YANG¹^,²

^1.State Key Laboratory of Advanced Electromagnetic Engineering and Technology (School of Electrical and Electronic Engineering, Huazhong University of Science and Technology), Wuhan 430074, Hubei Province, China
^2.International Joint Research Laboratory of Magnetic Confinement Fusion and Plasma Physics (School of Electrical and Electronic Engineering, Huazhong University of Science and Technology), Wuhan 430074, Hubei Province, China

Received:2024-08-01 Revised:2024-10-25 Published:2024-12-31 Online:2024-12-30
Contact: Chuan LI
Supported by:
National Key Research and Development Program of China(2022YFE03150102);National Natural Science Foundation of China(52207158);Interdisciplinary Research Program of HUST(2024JCYJ017)

摘要/Abstract

摘要：

目的为了真实反映聚变中子辐照特性损伤，有必要开展高通量聚变中子源的研究。磁约束氘氘聚变中子源预研装置是国际首台可实现场反等离子体大压缩比级联磁压缩的实验装置，作为该装置核心部件之一的磁压缩磁体，设计要求中心磁场的磁感应强度在500 μs内从0 T上升至7 T，为此，提出了针对磁压缩磁体导体部分的设计思路。方法围绕磁体的导体设计，从导体材料选取、导体匝间距离与导体径向厚度3方面入手，通过有限元仿真软件分析导体应力情况，得到了导体材料电导率、导体匝间距离以及导体径向厚度对导体应力的影响。结果确定了下一步磁体的设计思路，即在欧姆损耗允许的范围内适当选择电导率偏低的导体材料,在轴向空间允许的范围内通过增加绝缘层厚度的方式适当增加导体匝间距，在材料许用应力的范围内适当减小导体径向厚度以降低建设成本。结论随着中子源预研装置项目的进一步推进，所提出的设计思路可为磁压缩磁体装置的设计提供优化方向。

关键词: 可控核聚变, 磁压缩磁体, 聚变中子源, 大口径脉冲强磁体, 有限元分析, 氘氘聚变, 磁场

Abstract:

Objectives In order to truly reflect the damage characteristic of fusion neutron irradiation, it is necessary to carry out research on high-flux fusion neutron sources. As the first experimental device in the world that can realize cascaded magnetic compression with high compression ratio of field-reversed configuration plasma, the preliminary research device of magnetic confinement deuterium-deuterium fusion neutron source has important scientific significance. As one of the core components of the device, the magnetic compression magnet was designed to increase the magnetic induction intensity of the central magnetic field from 0 T to 7 T within 500 μs. Therefore, a design idea for the conductor part of the magnetic compression magnet was proposed. Methods Based on the conductor design of magnet, the conductor stress was analyzed by finite element simulation software from the three aspects of conductor material selection, conductor turn distance and conductor radial thickness. The influence of conductor material conductivity, conductor turn distance and conductor radial thickness on conductor stress was obtained. Results The design idea of the next magnet is determined. That is, the conductor material with low conductivity is appropriately selected within the allowable range of ohmic loss, the conductor turn spacing is appropriately increased by increasing the thickness of the insulation layer within the allowable range of axial space, and the radial thickness of the conductor is appropriately reduced within the allowable range of material stress to reduce the construction cost. Conclusions With the further development of the preliminary research device of neutron source project, the design ideas proposed in this paper can provide optimization direction for the design of magnetic compression magnet device.

Key words: controllable nuclear fusion, magnetic compression magnet, fusion neutron source, large-size pulsed high-field magnet, finite element analysis, deuterium-deuterium fusion, magnetic field

中图分类号:

TK 01

周渝深, 潘垣, 李传, 饶波, 杨勇. 氘氘聚变中子源大口径强磁场磁压缩磁体的设计与优化[J]. 发电技术, 2024, 45(6): 1016-1022.

Yushen ZHOU, Yuan PAN, Chuan LI, Bo RAO, Yong YANG. Design and Optimization of Deuterium-Deuterium Fusion Neutron Source Large-Size and High Magnetic Field Magnetic Compression Magnet[J]. Power Generation Technology, 2024, 45(6): 1016-1022.

图/表 14

图1 磁约束氘-氘聚变中子源预研装置示意图

Fig. 1 Schematic diagram of the preliminary research device of magnetic confinement deuterium-deuterium fusion neutron source

图2 磁压缩磁体示意图

Fig. 2 Schematic diagram of compression magnet

图3 线圈组结构示意图

Fig. 3 Structure diagram of coil group

图4 仿真模型示意图

Fig. 4 Schematic diagram of simulation model

表1 长度的具体参数

Tab. 1 Specific parameters oflength

参数		长度/mm
参数		L₁	L₂	L₃	L₄
匝间距/mm	6	2 000	189	230	212
	10	2 000	167	250	220
	14	2 000	145	270	228
径向厚度/mm	150	2 000	145	270	178
	175	2 000	145	270	203
	200	2 000	145	270	228

表2 导体材料电气参数

Tab. 2 Electrical parameters of conductor material

材料	相对介电常数 $ε r$	相对磁导率 $μ r$	体积电导率 $σ$ /(MS/m)
纯铜	1	0.999 991	58
B30白铜	1	1.03	4.7

表2 导体材料电气参数

Tab. 2 Electrical parameters of conductor material

材料	相对介电常数 $ε r$	相对磁导率 $μ r$	体积电导率 $σ$ /(MS/m)
纯铜	1	0.999 991	58
B30白铜	1	1.03	4.7

表3 线圈组材料结构参数

Tab. 3 Coil group material structure parameters

材料	杨氏模量/GPa	泊松比	许用应力/MPa
纯铜	120	0.343	70
B30白铜	150	0.32	200
环氧树脂	24	0.13	250

图5 不同导体材料各径向位置的磁感应强度曲线图

Fig. 5 Curves of magnetic induction intensity at each radial position of different conductor materials

图6 不同导体材料峰值电流密度云图

Fig. 6 Peak current density cloud map of different conductor materials

图7 不同导体材料线圈组等效应力云图

Fig. 7 Equivalent stress nephogram of coil groups with different conductor materials

图8 不同匝间距线圈组等效应力云图

Fig. 8 Equivalent stress nephogram of coil group with different turn spacing

图9 不同绝缘层厚度下磁感应强度曲线图

Fig. 9 Curve of magnetic induction intensity under different insulating thicknesses

图10 不同径向厚度的线圈组等效应力云图

Fig. 10 Equivalent stress nephogram of coil groups with different radial thicknesses

表4 不同径向厚度的线圈组各法向应力最大值

Tab. 4 Maximum normal stress of coil group with different radial thicknesses

径向厚度/mm	等效应力/MPa	径向应力/MPa	轴向应力/MPa	环向应力/MPa
150	191.47	-57.80	-49.58	173.41
175	172.21	-58.89	-49.99	154.31
200	159.44	-59.61	-50.23	140.12

参考文献 16

1	张一鸣．ITER计划和核聚变研究的未来[J]．真空与低温，2006，12(4)：231-237． doi:10.3969/j.issn.1006-7086.2006.04.011
	ZHANG Y M ．Iter program and the future of nuclear fusion research[J]．Vacuum and Cryogenics，2006，12(4)：231-237． doi:10.3969/j.issn.1006-7086.2006.04.011
2	HUANG J， LIU H C， GAO Z，et al ．Helium-hydrogen synergistic effects in structural materials under fusion neutron irradiation[J]．Frontiers in Materials，2022，9：49． doi:10.3389/fmats.2022.849115
3	GILBERT M R， SUBLET J C ．Scoping of material response under DEMO neutron irradiation：comparison with fission and influence of nuclear library selection[J]．Fusion Engineering and Design，2017，125：299-306． doi:10.1016/J.FUSENGDES.2017.06.016
4	潘垣，王之江，武松涛，等．基于场反位形的磁约束氘氘脉冲聚变中子源方案设计[J]．中国工程科学，2022，24(3)：205-213． doi:10.15302/J-SSCAE-2022.03.021
	PAN Y， WANG Z J， WU S T，et al ．Project design of a pulsed D-D fusion neutron source based on field reversed configuration[J]．Strategic Study of CAE，2022，24(3)：205-213． doi:10.15302/J-SSCAE-2022.03.021
5	PAN Y， WU S， WANG Z，et al ．A new device concept of magnetic confinement deuterium-deuterium fusion[J]．Chinese Physics Letters，2023，40(10)：102801． doi:10.1088/0256-307x/40/10/102801
6	REJ D J， TAGGART D P， BARON M H，et al ．High-power magnetic-compression heating of field-reversed configurations[J]．Physics of Fluids B，1992，4(7)：1909-1919． doi:10.1063/1.860043
7	SIMON R E， ARMSTRONG W T， BARNES D，et al ．Review of the Los-Alamos FRX-C experiment[J]．Fusion Technology，1986，9(1)：13-37． doi:10.13182/fst86-a24698
8	TUSZEWSKI M ．Field reversed configurations[J]．Nuclear Fusion，1988，28：2033． doi:10.1088/0029-5515/28/11/008
9	KITANO K， MATSUMOTO H， YAMANAKA K，et al ．Advanced experiments on field-reversed configuration at Osaka[J]．Physics of Plasmas，1995，191(2)：32-35．
10	张义雄．HFRC磁压缩场反等离子体装置的压缩区设计[D]．武汉：华中科技大学，2020． doi:10.1109/tps.2020.2987038
	ZHANG Y X ．Compression region design of HFRC magnetic compression field anti-plasma device[D]．Wuhan：Huazhong University of Science and Technology，2020． doi:10.1109/tps.2020.2987038
11	ZHANG Q， RAO B， YANG Y，et al ．Structural optimization design and numerical analysis of in-vessel magnetic compression coils[J]．Fusion Engineering and Design，2023，192：113780． doi:10.1016/j.fusengdes.2023.113780
12	汪献伟，王兆亮，刘小刚，等．CFETR模型线圈引线的力学分析[J]．核聚变与等离子体物理，2016，36(1)：60-64． doi:10.16568/j.0254-6086.201601011
	WANG X W， WANG Z L， LIU X G，et al ．Mechanical analysis of feeder for CFETR CS model coil[J]．Nuclear Fusion and Plasma Physics，2016，36(1)：60-64． doi:10.16568/j.0254-6086.201601011
13	赵善焕．CFETR中心螺线管线圈结构设计和电磁分析[D]．合肥：中国科学技术大学，2014．
	ZHAO S H ．Structural design and electromagnetic analysis of CFETR central solenoid coil[D]．Hefei：University of Science and Technology of China，2014．
14	BRUN C， NGUYEN C， DECOOL P，et al ．ITER central solenoid precompression test mock-up-validation phase to prepare the assembly on-site[J]．Fusion Engineering and Design，2023，194：113705． doi:10.1016/j.fusengdes.2023.113705
15	陈光．CFETR中心螺线管模型线圈结构[D]．合肥：合肥工业大学，2018．
	CHEN G ．CFETR center solenoid model coil structure[D]．Hefei：University of Science and Technology of China，2018．
16	LÜ Y L， ZHANG Q L， WU T，et al ．Optimization of the pulsed high-field coil in a magnetic trap type plasma compression device[J]．IEEE Transactions on Applied Superconductivity，2020，30(4)：1-5． doi:10.1109/tasc.2020.2968261

氘氘聚变中子源大口径强磁场磁压缩磁体的设计与优化

Design and Optimization of Deuterium-Deuterium Fusion Neutron Source Large-Size and High Magnetic Field Magnetic Compression Magnet

RichHTML

PDF (PC)

可视化

摘要/Abstract

引用本文

图/表 14

参考文献 16

相关文章 1

编辑推荐

Metrics