面向等离子体材料钨中氘/氦滞留行为的研究进展

作为面向等离子体材料,钨(W)在服役的过程中不仅受到等离子体造成的高能热负荷的作用,还受到高束流粒子如氘(D)、氚(T)、氦(He)等的轰击和D-T聚变反应产生的高能中子的影响.W中D、T、He的滞留和起泡,仍是聚变堆装置中有待解决的关键问题之一.综述了D、T和He的滞留行为及其气泡形成与辐照条件之间的关系,简要评述了W的服役性能和强化机理.通过降低W中D/He滞留量、抑制气泡的形成可有效改善W的服役性能.深入研究D/He滞留行为与辐照缺陷之间的相互作用关系,进而构建D/He的宏观热脱附行为与其微观状态之间的对应关系,为寻找合适途径来改善W的服役性能提供理论支撑.     

嬗变元素Re、Os对聚变装置面向等离子体钨材料性能的影响

钨(W)由于具有高熔点、高密度、低热膨胀系数、低氚滞留、低溅射产额等优异性能,被认为是最有潜力的聚变装置面向等离子体材料.氘氚聚变反应产生的14 MeV中子会导致W中嬗变元素铼(Re)、锇(Os)的产生,随着服役时间的延长,嬗变元素不断累积.这两种嬗变元素的产生势必会影响到W材料的微观组织结构,进而对W材料的性能产生影响.本文全面介绍了W嬗变元素Re、Os对聚变装置面向等离子体W材料的关键服役性能的影响,包括对力学性能、抗辐照性能、热学性能以及钨中氢同位素输运行为的影响.结果表明,W嬗变元素Re、Os能对W材料的性能造成较大的改变,但目前相关的研究都不够系统化,未来还需进行更为系统的研究来全面地对中子辐照条件下聚变装置面向等离子体W材料的性能进行评估.     

氦离子辐照对钨纳米丝稳定性的影响

用150 eV高能氦(He)离子在400 K对多晶钨(W)表面的W纳米丝进行间歇式辐照并使用扫描电子显微镜、透射电子显微镜以及称重法等手段对其表征,研究了He离子辐照对W纳米丝演变过程的影响。结果表明,高能He离子辐照使W纳米丝极不稳定。随着辐照剂量的增加W纳米丝之间的交联程度逐渐降低。W丝内的He泡在高能He离子溅射的作用下破裂,使W丝塌陷合并,部分溅射出来的W原子沉积在近邻的W纳米丝外壁或W丝根部,最终使W纳米丝演变成顶部细根部粗的锥型结构。     

氘在低活化铁素体/马氏体钢相关再沉积层中的热脱附行为

采用直流磁控溅射法,在氩气和氘气混合气氛下溅射金属靶制备铁、铬及钨与氘的共沉积层,模拟核聚变装置中燃料等离子体作用下低活化铁素体/马氏体(RAFM)钢第一壁材料表面再沉积层。分别考察了在磁控溅射腔室及直线等离子体模拟装置两种平台下,氘等离子体辐照对RAFM钢相关再沉积层中氘热脱附与滞留行为的影响。研究结果表明:氘与金属共沉积的RAFM钢相关涂层中,氘热脱附行为因受材料本身的组分和结构影响而存在差异;不同的氘等离子体辐照环境对氘在共沉积涂层中捕获形式的影响不同;总体而言,两种氘等离子体辐照后,均有大量氘滞留在RAFM钢相关再沉积层中,且氘总滞留量随氘等离子体辐照通量的增大而增大;铁基和钨基涂层中的氘滞留总量相当,均比铬基的低出1-2个数量级。     

核聚变第一壁用W-ZrC材料研究进展与展望

核聚变能是利用氢同位素氘与氚进行聚变反应而释放出的巨大能量来发电。而材料问题尤其是面向等离子体材料(PFMs)一直是核聚变能发展面临的主要挑战之一。由于PFMs直接包围高温等离子体,不但要承受高热负荷(5~20 MW/m~2稳态热流,GW/m~2级瞬态热流),而且还经受高通量的高能中子辐照、等离子体燃料粒子等的轰击等。钨(W)具有高熔点、高溅射阈值/低溅射率和高热导率等优点,而被认为是最有希望的面向等离子体第一壁的材料,目前ITER及EAST已经选用纯W作为第一壁及偏滤器材料。而对于下一代聚变堆如中国聚变工程实验堆(CFTER),其设计参数更高,PFMs服役环境比ITER及EAST更加严峻。因此纯W由于一些自身的弱点如低温脆性(DBTT~400℃)、再结晶脆化以及辐照脆化、高热负荷开裂熔化、等离子刻蚀严重等不足将无法满足未来需求。因此研究材料的辐照损伤与氢氦效应机理,揭示辐照引起材料微观结构与性能的变化以探索开发新型抗辐照W基第一壁材料变得十分迫切。近年来,国内外研究人员针对上述问题开展了系统的研究工作,研发了不同种类的W基复合材料,如W-Y_2O_3、W-La_2O_3、W-TiC及W-ZrC等,性能及工艺均取得了一定的进展。其中基于计算模拟结果发展的W-ZrC材料具有较好的综合性能,是未来聚变装置第一壁候选材料之一。本文系统介绍了W-ZrC材料研究进展,包括:钨中辐照损伤/氢氦效应机理、界面耦合强化的计算模拟结果、微结构分析测试及服役性能评估的研究,通过全面的总结分析,提出W基第一壁材料今后的主要研究方向,以及研发高性能面向未来聚变堆第一壁材料应采取的策略及措施。     

不同辐照粒子下钨及钨合金辐照损伤行为的研究进展

研究核聚变、准稳态等离子体下面向等离子体材料的辐照行为,发展适合于先进实验超导托卡马克(EAST)、国际热核聚变实验堆(ITER)和中国聚变工程实验堆(CFETR)长脉冲高参数运行乃至未来聚变反应堆稳态运行的高性能面向等离子体材料是当前核聚变研究一项艰巨而又紧迫的任务。钨因具有高熔点、高导热率、低溅射腐蚀速率、高自溅射阀值以及低蒸气压和低氚滞留等优异性能,被认为是聚变装置最具有前景的面向等离子体材料。综合评述了钨及钨合金在不同辐照粒子下损伤行为的最新研究进展。粒子辐照造成的微观缺陷在钨及钨合金内部累积,辐照造成缺陷的形成和数量与钨基材料颗粒微观结构、第二相成分等密切相关,辐照缺陷情况各异。同时,辐照粒子种类、能量、剂量和温度等辐照条件都会对钨材料辐照后的形貌特征和缺陷产生重要影响。     

氘、氚与RAFM钢相容性研究进展

核聚变能是解决人类能源危机和环境问题最有效的途径,其主要是利用氘氚聚合释放的能量。磁约束聚变是目前最可能实现受控热核聚变的方法,但要实现长期且稳态的核聚变反应还面临着诸多挑战,其中材料的研究与开发是聚变堆能否商业化的关键。在服役过程中,包层结构材料不仅受到高热负荷及强腐蚀作用,还受到各种粒子如氘(D)、氚(T)、氦(He)等的轰击和D-T聚变反应产物高能中子的影响。目前,确定的候选结构材料主要有奥氏体不锈钢、低活化铁素体/马氏体(RAFM)钢、钒合金以及碳化硅复合材料四种。而RAFM钢因具有低活性、较低的热膨胀系数、较高的热导率、辐照环境下具有较好的几何稳定性被选为目前最具前景的结构材料。获得氘氚在RAFM钢中的输运参数是未来核数据库建立的基础和前提,近几年关于氘在RAFM钢中输运行为的研究较多,然而不同研究者所得的结果差别很大,且缺乏实际的氚实验的基础数据。因此建立实验测试标准十分必要。RAFM钢主要以板条马氏体结构为主,具有较高的氘、氚渗透率,极易造成氘氚燃料的损失及氚放射性污染。因此,必须减少或避免RAFM钢与氘氚的直接接触。在RAFM钢表面制备一定厚度的阻氚涂层是实现氚自持最有效的途径之一。目前,国内外研究较多的阻氚涂层为Al2O3涂层,其阻氚因子可达103,且已实现工程化应用。此外,RAFM钢在服役过程中产生的辐照损伤及表面状态变化必然会影响氘氚的输运行为,主流观点认为辐照产生的缺陷会增加氘氚在金属材料中的滞留量,当材料中氘原子浓度达到10-6时,塑韧性下降,产生氢脆,尤其对于氚,衰变产生的He-3原子浓度达到10-9时,还会引发更严重的氦脆。除了制备阻氚涂层外,最近的研究多致力于通过成分调控及改善热处理工艺来提高RAFM钢的抗氢性能及抗辐照性能。本文归纳了氘氚在RAFM钢中行为的研究进展,分别对RAFM钢中氘氚渗透和滞留行为及其对力学性能的影响等进行介绍,分析了RAFM钢开发面临的问题并展望其前景,期望为RAFM钢数据库的建立以及服役于聚变堆的工程可行性提供参考。     

纳米多晶钨膜中He相关缺陷对H滞留的影响*

用磁控溅射方法制备纳米多晶钨膜, 采用X射线衍射(XRD), 扫描电子显微镜(SEM), 弹性反冲探测(ERD)和慢正电子束分析(SPBA)等手段研究了在高能He⁺和H⁺依次对其辐照后He相关缺陷对H滞留的影响。结果表明, 注He⁺钨膜在退火后从β型钨向α型钨转变; 钨膜中的He含量随着退火温度的提高而减少, 在873 K退火加剧钨膜中He原子的释放, 且造成钨膜空位型缺陷的增加和结构无序度的提高; 钨膜中的H滞留总量随着He滞留总量的减少略有下降。     

D~+注入对Li_4SiO_4表面形貌影响的研究

国际热核聚变堆采用氚增殖剂与中子反应产生氚,其中氚增殖剂的释放行为和辐照性能是聚变堆设计研究的重要内容,中国独立发展的氦冷固态球床实验包层初步采用硅酸锂作为氚增殖剂。本文采用氢的同位素氘模拟研究氚在增殖剂中的释放行为和辐照性能,通过离子注入方式对硅酸锂陶瓷进行了不同剂量的氘离子辐照,研究了D离子注入对硅酸锂表面形貌的影响,同时采用高温热解析技术研究了D在硅酸锂中的释放行为。结果表明:D离子注入在表面形成了微米级气泡带、纳米级微孔、无规则裂缝。在加热过程中D主要以HD、D_2、HDO、D_2O形态释放。     

He~+辐照对非晶碳氢薄膜表面硬度的影响

在室温下,利用等离子体增强的化学气相沉积法(PECVD)在硅衬底上制备了非晶碳氢薄膜。采用100keV,剂量分别为1.0×1015、5.0×1015、5.0×1016和1.0×1017ions/cm2的He离子(He+)对非晶碳氢薄膜进行辐照实验。通过基于原子力显微镜(AFM)的纳米压痕和纳米划痕技术,对He+辐照前后碳氢薄膜的表面硬度进行分析。结果表明,经He+辐照后碳氢薄膜的表面硬度明显增加,并且随着He+辐照剂量增加,碳氢薄膜的表面硬度呈逐渐增加的趋势。傅里叶变换红外光谱(FT-IR)和拉曼光谱分析表明,He+辐照会导致碳氢薄膜中sp2C键含量明显增加,而sp3C键及H原子的含量明显降低,这可能是引起碳氢薄膜硬度变化的主要原因。     

Research and development of nanocrystalline W/W-based materials: novel preparation approaches,formation mechanisms,and unprecedented excellent properties

Tungsten (W) has become the most promising plasma-facing material (PFM) in fusion reactor, and W still faces performance degradation caused by low-temperature brittleness, low recrystallization temperature, neutron irradiation effects, and plasma irradiation effects. The modification of W/W-based materials in terms of microstructure manipulation is needed, and such techniques to improve the performance of materials are the topics of hot research. Researchers have found that refining the grain can significantly improve the strength and the irradiation resistance of W/W-based materials. In this paper, novel approaches and technique routes, including the “bottom-up” powder metallurgy method and “top-down” severe plastic deformation method, are introduced to the fabrication of nanocrystalline W/W-based materials. The formation mechanisms of nanocrystalline W/W-based materials were revealed, and the nanostructure stabilization mechanisms were introduced. The mechanical properties of nanocrystalline W/W-based materials were tested, and the irradiation behaviors and performances were studied. The mechanisms of their high mechanical properties and excellent irradiation-damage resistance were illustrated. This article may provide an experimental and theoretical basis for the design and development of high-performance novel nanocrystalline W/W-based materials.     

Plasma-surface interaction in ITER

The decreasing availability of energy and the concern about climate change necessitate the development of novel sustainable energy sources. Fusion energy is such a source. The ultimate potential of fusion energy is very high and badly needed. A major step forward in the development of fusion energy is the decision to construct the experimental test reactor ITER.ITER will stimulate research in many areas of science. This article discusses research opportunities in the context of plasma-surface interaction. The fusion plasma with a typical temperature of 10 keV has to be brought into contact with a physical wall in order to remove the helium produced and drain the excess energy in the fusion plasma. The fusion plasma is far too hot to be brought into direct contact with a physical wall. It would degrade the wall and the debris from the wall would extinguish the plasma. Therefore, schemes are developed to cool down the plasma. The resulting plasma-surface interaction concerned in ITER is facing several challenges including surface erosion, material redeposition and tritium retention. In this article we introduce how plasma-surface interaction relevant for ITER can be studied in a smaller scale experiment: Magnum-PSI.     

Service Behavior of Multifunctional Triboelectric Nanogenerators

Triboelectric nanogenerators (TENGs) or TENG‐based self‐charging systems harvesting energy from ambient environment are promising power solution for electronics. The stable running remains a key consideration in view of potential complex application environment. In this work, a textile‐based tailorable multifunctional TENG (T‐TENG) is developed. The T‐TENG is used as self‐powered human body motion sensor, water energy harvester, and formed all textile‐based flexible self‐charging system by integrating with textile‐based supercapacitors. The service behavior and the mechanism of performance retention are also studied when the T‐TENG is damaged. As a self‐powered human body motion sensor, the T‐TENG maintains the stable properties when it is cut. As a water energy harvester, the T‐TENG is capable of scavenging mechanical energy from water efficiently even if it is damaged partly. Besides, the charge properties of the self‐charging system are systematically investigated when the T‐TENG is cut. The investigation on service behavior of T‐TENG and TENG‐based self‐charging system pushes forward the development of highly reliable electronics and is a guide for other nanodevices and nanosystems.     

Experimental investigation of the film boiling heat transfer in He II: Heat transfer coefficient

He II film boiling is of both academic and applied interests. However, information about He II film boiling is still inadequate and further study is needed from both the technical application and the scientific aspects. In the present study, a thin stainless steel foil heater (10 μm thick) is employed to induce boiling in He II. The average heater surface temperature is measured to evaluate the heat transfer performance of He II film boiling under different thermal conditions. And meanwhile, the pressure and the temperature oscillations induced by the film boiling are also measured. It is found that the pressure oscillation and the temperature oscillation highly correlate with each other, which indicates that the vapor bubble is vibrating on the heater surface during film boiling. The heat transfer coefficient of the film boiling depends on both the pressure over the heater surface and the He II bath temperature. The heat transfer coefficients of three kinds of boiling states: noisy film boiling, transition boiling and silent film boiling, are measured in the present study. The visualization of the boiling process is also carried out.     

Studies of carbon behavior in tungsten under carbon and hydrogen mixed irradiation

The erosion of W coatings with the different content of C was investigated in Ar and Ar + H₂ plasmas. The enhanced erosion was registered in Ar + H₂ plasma for coatings containing 40 at.% of C and more, which might be owing to chemical erosion of carbon. The erosion kinetics was analyzed together with the studies of coatings microstructure, phase composition and Vicker hardness properties.The C distribution profiles in W were investigated in dependence on the redeposition rate of sputtered C and simultaneous 0.3 keV Ar⁺ ion irradiation. It is shown that C penetration depth depends on the coverage of W by C during ion irradiation. Deep C penetration was registered when W was partially covered by redeposited carbon.The computer simulation was used to extrapolate obtained results to experimental investigations performed by Ueda Y, Fukumoto M, Sawamura I, Sakizono D, Shimada T, Nishikawa M. [Fusion Eng Des 2006;81:233–9]. It is revealed that the ballistic relocation of implanted C atoms is the dominant process which explains the deep penetration of C and formation of WC compound in the near-surface region of W.     

紫外分步辐照接枝制备亲水性荷负电纳滤膜

通过在聚醚砜(PES-C)微孔膜表面紫外分步辐照接枝甲基丙烯酸羟乙酯(HEMA)和苯乙烯磺酸钠(SSS)制备了一种新型的亲水性荷负电纳滤膜。通过测定膜的纯水通量和对不同盐溶液的表观截留率的变化,系统研究了制备条件对膜分离性能的影响。结果表明,采用该方法制成的纳滤膜对高价阴离子盐溶液Na2SO4的表观截留率和渗透通量都较高,如HEMA先辐照接枝120s、SSS再继续接枝15min制得的膜对Na2SO4截留率大于95%,而渗透通量则高达19.02L/(m2.h)。     

He+ 辐照对CLAM钢焊缝微观组织和性能的影响

在室温下用强度为70 keV的He⁺辐照CLAM钢焊缝,使用扫描电子显微镜(SEM)、透射电子显微镜(TEM)和连续刚度纳米压痕技术(CSM)对其表征,研究了He⁺辐照对CLAM钢焊缝的微观组织和性能的影响。结果表明,随辐照剂量的增大焊缝表面黑色孔洞的尺寸增大、密度提高;辐照剂量为1×10¹⁷ ions·cm^-2时,在两种焊缝中形成的位错环的尺寸分别约为18.97 nm、15.73 nm,数密度分别约为2.24×10²¹ m^-3、1.78×10²¹ m^-3,氦泡引起的辐照肿胀率分别约为1.7%和0.4%;辐照缺陷(位错环、氦泡)导致的辐照硬化率分别为49.0%和29.9%。与焊态焊缝相比,调质处理态焊缝的辐照损伤较弱,在一定程度上表明经调质处理后焊缝的抗辐照性能有所提高。