CFETR中心螺管模型线圈用316LN异型铠甲力学性能研究

改良后的316LN不锈钢因为其在低温下优异的延展性能,被选作为中国聚变工程实验堆(CFETR)中心螺线管(CSMC)的铠甲材料。主要对316LN铠甲材料进行了室温与低温下的力学性能测试,并进行了统计分析。实验结果表明316LN铠甲拥有非常好的拉伸性能。     

ITER TF超导体焊缝的氦质谱气密性检测

国际热核聚变实验反应堆(ITER)磁体环场线圈TF导体采用CICC(cable in conduit conductor)导体结构,其导管为316LN型不锈钢套管。文中针对ITER项目对导体气密性要求,主要介绍了超导体导管焊缝的氦质谱气密性检测技术方法、检测系统、检测流程和漏率计算。     

不同条件下聚变用316LN不锈钢铠甲的力学性能研究北大核心

ITER计划中纵场线圈采用管内电缆导体结构,简称CICC结构。由于无磁性的奥氏体不锈钢是核聚变反应堆的理想材料,导体铠甲采用的是材质为改良的316LN无缝不锈钢管。ITER TF线圈的CICC导体套管由316LN不锈钢管接而成。再将电缆穿入铠甲中经过冷作硬化后,进行650℃/200h的时效热处理,最终在导体运行期间,温度降至4.2K的液氦温度下服役。对于导体铠甲能否经受以上加工处理,将对聚变用316LN不锈钢铠甲在不同的形变、热处理温度和不同温度下的力学性能进行比较分析。     

不同条件下聚变用316LN不锈钢铠甲的力学性能研究

ITER计划中纵场线圈采用管内电缆导体结构,简称CICC结构。由于无磁性的奥氏体不锈钢是核聚变反应堆的理想材料,导体铠甲采用的是材质为改良的316LN无缝不锈钢管。ITER TF线圈的CICC导体套管由316LN不锈钢管接而成。再将电缆穿入铠甲中经过冷作硬化后,进行650℃/200h的时效热处理,最终在导体运行期间,温度降至4.2K的液氦温度下服役。对于导体铠甲能否经受以上加工处理,将对聚变用316LN不锈钢铠甲在不同的形变、热处理温度和不同温度下的力学性能进行比较分析。     

ITER PF线圈滑动衬垫MoS_2基固体自润滑涂层工艺研究

研究了在316LN不锈钢板材表面涂覆二硫化钼基自润滑涂层来增加其耐磨性能的方法,此涂层性能优异,与基底之间的结合强度高,室温和77K液氮温度下进行热冲击试验后,涂层表面未出现裂纹,在高载荷(80MPa)、长周期(30000周期)、低温条件下磨损后不失效,满足ITER要求。     

FAIR项目super-FRS超导磁体结构分析

 国际反质子与离子大科学工程项目中的超导super-FRS磁体包含2个超导线圈,最大磁场为1.6 T,这样大的磁场必然产生很大的电磁力。为了保证磁体运行时的机械稳定性,对项目中的超导super-FRS磁体进行了有限元结构的3维分析。结构分析中采用了ADINA和TOSCA两个有限元软件。ADINA软件主要用于结构中的应力应变计算,而TOSCA软件则主要用于电磁场的磁场强度和电磁力的计算。分析的结果显示super-FRS磁体采用铁芯及线圈盒长边中部加固结构时,其最大形变约0.19 mm,最大有效应力出现在长边中部的很小区域,约为92 MPa。由于线圈盒由316LN不锈钢制成,该结构是合理的。     

ITER TF铠甲焊缝力学性能研究

ITER TF线圈的CICC导体套管由316LN不锈钢管采用氩孤焊自熔对焊连接而成.选择三种不同的316LN不锈钢管为研究对象,它们分别为母材管、焊接未变形管和焊接后经过8%的冷作变形和650℃下200小时的老化处理的316LN不锈钢管,在室温下对这三种型号的不锈钢管进行拉伸试验,对前两种材料进行冲击试验,同时在4.2...     

CFETR CS模型线圈的电磁分析

在中国聚变工程试验堆(CFETR)的概念设计阶段,为了将来正确设计和顺利加工其中心螺线管(CS)线圈,设计了一个由Nb₃Sn内线圈和NbTi外线圈组成的模型线圈。采用线电流模型和后期数据处理的方法对其磁场做了精确计算,解决了线电流模型不能计算导线内部磁场的问题。在此基础上计算了线圈的电感和电磁应力等参数。     

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在中国聚变工程试验堆(CFETR)的概念设计阶段,为了将来正确设计和顺利加工其中心螺线管(CS)线圈,设计了一个由Nb3Sn内线圈和NbTi外线圈组成的模型线圈。采用线电流模型和后期数据处理的方法对其磁场做了精确计算,解决了线电流模型不能计算导线内部磁场的问题。在此基础上计算了线圈的电感和电磁应力等参数。     

CRAFT TF Dummy 线圈 VPI 模具设计与分析

环向场(Toroidal Field, TF) 线圈是聚变堆主机关键系统综合研究设施(CRAFT) 的重要组成部分, 由CICC(Cable in Conduit Conductor) 导体完成线圈绕制, 通过真空压力浸渍(Vacuum Pressure Impregnation, VPI)完成线圈绝缘处理. 在树脂浸渍线圈绝缘层, 随后进行较长时间的高温固化, 以完全固化整个绝缘层的树脂. 在浸渍和固化过程中,VPI 模具不仅承受线圈本身的载荷, 还要承受大气压力、 内部打压、 热变形等. 为了保证线圈绝缘质量, 采用 CATIA 软件对 VPI 模具进行3D 建模, 并对 VPI 模具进行了 Ansys Workbench 有限元软件分析与校核. 分析表明,VPI 模具的设计合理, 为工程设计提供了理论和实践依据.     

Deuterium transport and isotope effects in type 316L stainless steel at high temperatures for nuclear fusion and nuclear hydrogen technology applications

We present the first complete data set for the permeability, diffusivity, and solubility of both deuterium and hydrogen in 316L stainless steel (316L SS) obtained over a wide temperature range of 350–850 °C that accommodates both nuclear fusion and nuclear hydrogen technology applications. The deuterium results were also compared with the hydrogen results to estimate the isotope effect. The isotope effect ratio for diffusivity was different from the classical prediction. Furthermore, some of our results were compared with the results previously reported for 316 SS. Results and discussion are presented with an emphasis on the deuterium permeation and isotope effects.     

焊后热处理对核聚变用316LN焊接接头的影响

采用了TIG对核聚变用316LN奥氏体不锈钢进行焊接,并对焊接接头进行了焊后热处理,利用光学显微镜、扫描电镜分析手段研究了焊后热处理对焊接接头微观组织和力学性能的变化。试验结果表明,焊缝中为奥氏体组织,并未发现第二相析出物存在。焊后热处理对接头的拉伸性能影响不大,均断裂在母材位置,但显著提高了接头的延伸率。接头低温冲击试验也展现了良好的抗低温冲击性能。断口分析发现,接头呈韧性断裂。     

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采用了TIG对核聚变用316LN奥氏体不锈钢进行焊接,并对焊接接头进行了焊后热处理,利用光学显微镜、扫描电镜分析手段研究了焊后热处理对焊接接头微观组织和力学性能的变化.试验结果表明,焊缝中为奥氏体组织,并未发现第二相析出物存在.焊后热处理对接头的拉伸性能影响不大,均断裂在母材位置,但显著提高了接头的延伸率.接头低温冲击试验也展现了良好的抗低温冲击性能.断口分析发现,接头呈韧性断裂.     

聚变堆用CLF-1 钢与316L 钢TIG 焊接接头组织与性能初步研究

对用W19123L 为焊丝的聚变堆用低活化CLF-1 钢与316L 钢的钨极氩弧焊(TIG)焊接接头金相组织及性能进行了初步研究。结果表明：焊接接头成型良好、无缺陷;金相组织表明焊接接头由CLF-1 侧(母材区、热影响区、熔合区)、过渡层、焊缝区、316L 侧(母材区、热影响区、熔合区)组成;室温拉伸试验结果优于母材的最低要求值;弯曲试验后的焊接接头内外表面完好,无裂纹产生,变形均匀;焊接接头冲击值成凹型分布,焊缝区冲击值最低,焊缝两侧热影响区冲击值次之,母材冲击值最高,316L 侧冲击值略高于CLF-1 侧,均满足焊接接头设计值;焊接接头上表面1.6mm 硬度波动较大,略高于1/2T 和下表面1.6mm 处,焊接接头1/2T 和下表面1.6mm 硬度分布较均匀,从CLF-1 侧到316L 侧有下降趋势。整体焊接性能基本稳定,满足异种钢焊接性能匹配要求。     

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A preliminary study of microstructure and properties of the welded joint of low activation CLF-1 steel used for fusion reactor and 316L dissimilar metal by tungsten inert gas (TIG) welding using W19123L as filler material, has been performed. The welded joint forming is proved well and without defect. The welded joint consists of CLF-1 zone [base metal (BM), heat affected zone (HAZ), fusion zone (FZ)], inside layer (IL), weld zone (WZ), and 316L zone (BM, HAZ, FZ). Tensile strength of the joint is better than the base metal minimum value in room temperature. Both surfaces of welded joint are without crack and with deformation uniformity under the bending test. The distribution of impact value of the joint is concave-like and satisfies the designed values for the welded joint, the WZ’s value is the lowest, the HAZ’s of both WZ zones is the second, the BM’s was the best, and the 316L steel zone’s is slightly larger than the CLF-1 zone’s. The hardness values of the point under the 1.6mm top surface of welded joint have a larger fluctuation range, and is slightly higher than those of 1/2T and above down surface 1.6mm position. The hardness distribution of 1/2T and above the down surface 1.6mm position is roughly uniform, and has a downward trend from the CLF-1 zone to 316L zone. Welding properties generally has remained stable and satisfy the requirement of dissimilar steel welding performance matching.     

Surface characterisation and electrochemical behaviour of porous titanium dioxide coated 316L stainless steel for orthopaedic applications

Porous titanium dioxide was coated on surgical grade 316L stainless steel (SS) and its role on the corrosion protection and enhanced biocompatibility of the materials was studied. X-ray diffraction analysis (XRD), atomic force microscopy (AFM), Fourier transform infrared (FTIR) spectroscopy, scanning electron microscopy (SEM) and energy dispersive X-ray analysis (EDAX) were carried out to characterise the surface morphology and also to understand the structure of the as synthesised coating on the substrates. The corrosion behaviour of titanium dioxide coated samples in simulated body fluid was evaluated using polarisation and impedance spectroscopy studies. The results reveal that the titanium dioxide coated 316L SS exhibit a higher corrosion resistance than the uncoated 316L SS. The titanium dioxide coated surface is porous, uniform and also it acts as a barrier layer to metallic substrate and the porous titanium dioxide coating induces the formation of hydroxyapatite layer on the metal surface.     

Exceptionally high cavitation erosion and corrosion resistance of a high entropy alloy

Cavitation erosion and corrosion of structural materials are serious concerns for marine and offshore industries. Durability and performance of marine components are severely impaired due to degradation from erosion and corrosion. Utilization of advanced structural materials can play a vital role in limiting such degradation. High entropy alloys (HEAs) are a relatively new class of advanced structural materials with exceptional properties. In the present work, we report on the cavitation erosion behavior of Al_0.1CoCrFeNi HEA in two different media: distilled water with and without 3.5 wt% NaCl. For comparison, conventionally used stainless steel SS316L was also evaluated in identical test conditions. Despite lower hardness and yield strength, the HEA showed significantly longer incubation period and lower erosion-corrosion rate (nearly 1/4th) compared to SS316L steel. Enhanced erosion resistance of HEA was attributed to its high work-hardening behavior and stable passivation film on the surface. The Al_0.1CoCrFeNi HEA showed lower corrosion current density, high pitting resistance and protection potential compared to SS316L steel. Further, HEA showed no evidence of intergranular corrosion likely due to the absence of secondary precipitates. Although, the degradation mechanisms (formation of pits and fatigue cracks) were similar for both the materials, the damage severity was found to be much higher for SS316L steel compared to HEA.     

The effect of TiN nanoparticles deposition with different number of shots on SS316L by plasma focus device

In this paper, we present the result of TiN nanocrystalline deposition on SS316L, using a 4 kJ plasma focus (PF) device for 10, 20, and 30 focus shots. The effect of different number of focus shots on micro-structural changes of thin film is characterized by field emission scanning electron microscope. Existence of grains in different size confirms the formation of TiN nanocrystals on the surface of SS316L substrate. X-ray diffraction (XRD) reveals the formation of a nanocrystalline titanium nitride coating on the surface of SS316L samples. The crystalline size of TiN obtained from XRD data is strongly dependent on the number of focus shots. Thickness of the elements found on the surface of the treated sample that obtain by Rutherford backscattering spectroscopy (RBS) analysis is in the range of 150×10¹⁵?200×10¹⁵ atoms/cm². All the existence elements in the coated samples are identified by Particle Induced X-ray Emission (PIXE) spectra. Investigation on the corrosion resistance of TiN coatings was performed using an electrochemical potentiodynamic polarization. Our results suggest that TiN nanocrystalline implantation with proper ion fluences using PF can significantly improve the corrosion resistance of SS316L.     

热管堆在不同基体材料下的燃耗特性分析北大核心CSCD

热管冷却核反应堆具有非能动传热、模块化和固有安全性高等特点,在航空探索、深海作业和偏远地区电力市场上有广泛的应用。以洛斯阿拉莫斯国家实验室开发的5 MWth热管堆为研究对象,选择SS-316,Mo-14Re和SiC作为基体候选材料,采用反应堆蒙特卡罗中子输运分析程序对比分析了以上三种基体堆芯的反应性、中子能谱、增殖性能和燃耗演化。结果表明:为了维持堆芯的10年运行,SS-316,Mo-14Re和SiC三种基体堆芯所需的初始燃料235U富集度分别约为19.35%,28.80%和17.10%,SiC基体堆芯所需的初始燃料235U富集度最小;10年后,SiC基体堆芯产生的易裂变核素(239Pu和241Pu)和次锕系核素(通过分离嬗变可被再次利用)的量最高,分别约为11.91 kg和92.08 g。综合以上研究结果,推荐SiC作为热管冷却核反应堆的基体。