高温液态锂与聚变堆结构材料润湿特性研究平台设计*

doi:10.13385/j.cnki.vacuum.2025.06.05

摘要/Abstract

摘要： 液态锂在基底材料表面的润湿性是决定液态锂第一壁性能的关键因素之一。设计了一套液态金属与固体材料润湿特性研究平台,结合系统运行关键问题,采用ANSYS软件对平台检测室和注射系统等部件进行了热力学仿真和理论计算。结果表明：外径250 mm、壁厚3 mm的304不锈钢真空检测室在一个大气压下的最大变形量约为0.045 mm,最大应力强度为29.876 MPa,低于许用应力（137 MPa）;检测室最大等效应力约26.708 MPa,低于不锈钢的屈服极限（205 MPa）;注射系统中加热丝温度为400 ℃时针头与加热丝的极限距离是50 mm;当注射器与检测室内部压差分别为600 Pa和-465 Pa时,液态锂可以通过1 mm口径的针头吸入和滴出;在系统运行过程中向检测室中充入0.26 Pa以上的氩气有利于保护检测室壁面和观察窗,减轻检测材料沉积的影响。基于以上结果,成功搭建了液态金属润湿实验平台,并实现了直径3 mm液态锂滴的滴出。

关键词: 润湿性, 液态锂, 第一壁, 注射系统

Abstract: The wettability of liquid lithium (Li) on the substrate surface is a key factor to determine the performance of the liquid Li first wall. A wettability research platform for the liquid metal and solid materials was designed, and the key problems of the platform are simulated and calculated theoretically. The ANSYS software was used to simulate the stress and heat distribution of the platform test chamber and injection system. The results show that the maximum deformation of 304 stainless steel test chamber with 250 mm outer diameter and 3 mm wall is about 0.045 mm, and the maximum stress intensity is 29.876 MPa, which is less than the allowable stress of 137 MPa under one atmosphere pressure. The maximum equivalent stress is about 26.708 MPa, which is less than the yield limit of 205 MPa. The limit distance between the needle and heating wire is 50 mm when the heating wire temperature is 400 ℃. When the internal pressure difference between the syringe and test chamber is 600 Pa and -465 Pa respectively, the liquid Li can be inhaled and dripped through a 1 mm diameter needle. During the operation of the system, filling the test chamber with argon gas of more than 0.26 Pa is conducive to protecting the wall and observation window of the test chamber, and reducing the influence of the detection material film. Based on the above results, the platform was successfully built and Li with a diameter of 3 mm was dripped out.

Key words: wettability, liquid lithium, first wall, nuclear fusion

中图分类号: TB79

杨龙, 孟献才, 梁立振, 闫振, 李旭, 张德皓, 左桂忠. 高温液态锂与聚变堆结构材料润湿特性研究平台设计^*[J]. 真空, 2025, 62(6): 31-38.

YANG Long, MENG Xiancai, LIANG Lizhen, YAN Zhen, LI Xu, ZHANG Dehao, ZUO Guizhong. Design of Wetting Research Platform for High-temperature Liquid Lithium with Structural Materials of Fusion Reactor[J]. VACUUM, 2025, 62(6): 31-38.

参考文献

[1] WANG Z, OREJON D, TAKATA Y, et al.Wetting and evaporation of multicomponent droplets[J]. Physics Reports, 2022, 960: 1-37.
[2] ZINKLE S.Briefing on and discussion of the results from the subcommittee dealing with materials science and technology research opportunities in the next 10-20 years[R]. FESAC-Materials-Science-Final-Report, 2012.
[3] 郭子成,罗青枝,荣杰. 润湿现象和毛细现象的热力学描述[J]. 大学物理,2000,19(6):19-21.
[4] 萨·杰拉,张红路. 润湿在印刷中的应用[J]. 印刷科技情报,1992(1):35-46.
[5] 段晓侠. 湿润疗法在压疮护理中的应用[J]. 中华全科医学,2009,7(4):429-430.
[6] 魏建华,封兴华,张浚睿,等. QCM-D技术在不同润湿性表面蛋白吸附研究中的应用[J]. 牙体牙髓牙周病学杂志,2008,18(7):396-398.
[7] BOLT H, BARABASH V, KRAUSS W, et al.Materials for the plasma-facing components of fusion reactors[J]. Journal of Nuclear Materials, 2004, 329: 66-73.
[8] RAFFRAY A R, NYGREN R, WHYTE D G, et al.High heat flux components—Readiness to proceed from near term fusion systems to power plants[J]. Fusion Engineering and Design, 2010, 85(1): 93-108.
[9] 章志涛,丁芳,罗宇,等. 小波阈值去噪在偏滤器光谱信号处理中的应用[J]. 量子电子学报,2022,39(3):307-315.
[10] KAPAT A, ALLAIN J P, BEDOYA F, et al.Liquid lithium wetting and percolation in a porous tungsten/liquid Li plasma facing component (PFC)[J]. Fusion Engineering and Design, 2022, 178: 113087.
[11] 吴玉程,盛学洋,马冰,等. 核聚变装置偏滤器靶板材料选择与研究进展[J]. 中国材料进展,2024,43(9):807-823.
[12] ONO M, JAWORSKI M A, KAITA R, et al.Recent progress in the NSTX/NSTX-U lithium programme and prospects for reactor-relevant liquid-lithium based divertor development[J]. Nuclear Fusion, 2013, 53(11): 113030.
[13] MAJESKI R, JARDIN S, KAITA R, et al.Recent liquid lithium limiter experiments in CDX-U[J]. Nuclear Fusion, 2005, 45(6): 519.
[14] MAZZITELLI G, APICELLA M L, FRIGIONE D, et al.FTU results with a liquid lithium limiter[J]. Nuclear Fusion, 2011, 51(7): 073006.
[15] MAZZITELLI G, APICELLA M L, RIDOLFINI V P, et al.Review of FTU results with the liquid lithium limiter[J]. Fusion Engineering and Design, 2010, 85(6): 896-901.
[16] HU J S, ZUO G Z, MAINGI R, et al.Experiments of continuously and stably flowing lithium limiter in EAST towards a solution for the power exhaust of future fusion devices[J]. Nuclear Materials and Energy, 2019, 18: 99-104.
[17] MIRNOV S V, BELOV A M, DJIGAILO N T, et al.Experimental test of the system of vertical and longitudinal lithium limiters on T-11M Tokamak as a prototype of plasma facing components of a steady-state fusion neutron source[J]. Nuclear Fusion, 2015, 55(12): 123015.
[18] ZUO G Z, LI C L, MAINGI R, et al.Results from a new flowing liquid Li limiter with TZM substrate during high confinement plasmas in the EAST device[J]. Physics of Plasmas, 2020, 27(5): 052506.
[19] FRANCIS C F J, KYRATZIS I L, BEST A S. Lithium‐ion battery separators for ionic‐liquid electrolytes: a review[J]. Advanced Materials, 2020, 32(18): 1904205.
[20] ZUO G Z, HU J S, MAINGI R, et al.Improvement on the plasma performances via application of flowing lithium limiters in EAST Tokamak[J]. Physica Scripta, 2020, 2020(T171): 014008.
[21] DE ANGELI M, LAGUARDIA L, MADDALUNO G, et al.Investigation on FTU dust and on the origin of ferromagnetic and lithiated grains[J]. Nuclear Fusion, 2015, 55(12): 123005.
[22] VERSHKOV V A, SARYCHEV D V, NOTKIN G E, et al.Review of recent experiments on the T-10 Tokamak with all metal wall[J]. Nuclear Fusion, 2017, 57(10): 102017.
[23] MORGAN T W, RINDT P, van EDEN G G, et al. Liquid metals as a divertor plasma-facing material explored using the Pilot-PSI and Magnum-PSI linear devices[J]. Plasma Physics and Controlled Fusion, 2017, 60(1): 014025.
[24] GÓMEZ-GARCÍA A, JIMÉNEZ D A A, ZAMORA W J, et al. Navigating the chemical space and chemical multiverse of a unified Latin American natural product database: LANaPDB[J]. Pharmaceuticals, 2023, 16(10): 1388.
[25] Tanke V F B, Al R S, ALONSO van der WESTEN S, et al. LiMeS-Lab: an integrated laboratory for the development of liquid-metal shield technologies for fusion reactors[J]. Journal of Fusion Energy, 2023, 42(2): 44.
[26] 范永山,杜畅通,张化一,等. XiPAF重离子同步加速器超高真空系统设计[J]. 工程科学与技术,2025,57(1):339-346.
[27] MENG X C, ZUO G Z, XU W, et al.Effect of temperature on the corrosion behaviors of 304 stainless steel in static liquid lithium[J]. Fusion Engineering and Design, 2018, 128: 75-81.
[28] 何惊华. 金属锂及氢化锂在水气氛中反应机理的理论研究[D]. 成都:四川师范大学, 2005.
[29] MENG X C, XU C, ZUO G Z, et al.Corrosion characteristics of copper in static liquid lithium under high vacuum[J]. Journal of Nuclear Materials, 2019, 513: 282-292.
[30] LYUBLINSKI I E, VERTKOV A V, EVTIKHIN V A.Application of lithium in systems of fusion reactors. 1. Physical and chemical properties of lithium[J]. Plasma Devices and Operations, 2009, 17(1): 42-72.
[31] 丘克强,段文军,陈启元. 金属在真空状态下的蒸发速率[J]. 有色金属,2002,54(2):48-52.

Metrics

Viewed

Full text

Abstract

Cited

Shared

Discussed