氚在不锈钢中的体扩散行为

采用酸液蚀刻法和液体闪烁法数法测量了在６７３Ｋ和１０１３Ｋ下分别充氚８ｈ、室温空气中时效１～３ａ后,３１６Ｌ型和２２－１３－５型不锈钢圆柱样品氚浓度的分布。运用扩散方程的有限差分数值解法,计算了样品中氚和氦－３的体浓度分布,结果与实验结果符合较好。研究结果表明,室温时效期间,氚在不锈钢中的扩散缓慢,主要通过衰变成氦－３后发生浓度变化;由于氧化层的影响,表面附近的氚只是部分逸出;样品中存在“固溶”和     

充氚不锈钢微观组织及断裂特征

采用力学拉伸实验测定充氚不锈钢的断裂强度值,采用拉伸断口进行SEM观察和正电子湮灭(PAT)分析,采用TEM动态拉伸实验观察和记录材料在微观断裂过程中的行为,通过对比分析氚对不锈钢断裂过程的影响。结果表明,高温充氚后,室温存放2a,样品中氚衰变产生的氦累积已达约30ppm;氚、氦使样品断裂强度降低,内部缺陷增多,正电子寿命变长。TEM观察未发现明显的氦泡组织;动态拉伸实验表明,充氚促进裂纹尖端位错的发射和增殖;HR-1、HR-2不锈钢微观断裂过程相似,可表述为氚致微裂纹的形核-形成微空洞-微空洞长大-空洞连接(断裂)。氚、氦使无位错区减小甚至消失。     

充氚不锈钢中氦行为的PAL和TEM研究

对充氚和未充氚的抗氢-2(HR-2)不锈钢样品进行退火处理,利用正电子湮没寿命谱(PAL)以及透射电镜(TEM)等技术探讨不锈钢中氦和微缺陷的相互作用。未充氚样品中,退火温度对缺陷态的影响主要表现为偏聚物在晶界的析出。充氚样品实验中,退火温度小于300℃时,充氚不锈钢中的He原子主要通过自捕获机制在晶内缺陷处聚集成泡;热处理温度为300～600℃时,充氚不锈钢中的He原子主要通过热迁移的方式迁移至晶界导致晶界宽化,但晶界处无明显的He泡形成;热处理温度大于600℃时,热平衡空位开始发挥作用,与聚集在晶内缺陷处的He原子结合形成He泡,且随退火温度的升高,He泡有明显聚合长大的现象。     

纯铝中氦泡分布特点的研究

将工业纯铝抛光后进行He离子注入，注入剂量为3×10²⁰ m^-2，注入能量为500 keV。利用SRIM软件模拟预测得离子注入后He原子在距表面1.8 μm处浓度最高。将He离子注入样品，在190 ℃时效192 h，促进氦泡的形成和长大，用透射电子显微镜观测样品深度方向上氦泡的分布。结果显示，距表面约1.8 μm处氦泡密度最大，说明 He原子浓度最高，与SRIM软件模拟预测结果一致。同时发现，晶界处氦泡的尺寸较晶粒内的大，说明晶界有利于氦泡的形成和长大；晶界两侧不同晶粒内氦泡尺寸有较大差异，可能是因为晶粒取向不同造成晶粒中氦泡的形核长大过程不同，说明晶粒取向对氦泡的合并长大行为可能有显著影响。     

氚污染部件干法去污技术

针对核退役工程中存在的大量含氚废物处理问题,利用设计组装的干法去污处理装置对氚污染的金属进行了加热、紫外线、臭氧去污研究.结果表明,升高温度可明显提高去污效果;220 ℃用365 nm紫外线照射3 h对不锈钢的表面去污效率可达99%;臭氧与加热联合作用更有利于提高去污效率,220 ℃时去污3 h,臭氧对不锈钢、铝、黄铜的去污效率可达95%以上;而去污完毕经放置后,金属的氚表面活度会有所增加.     

金属样品残余氚测量方法

为定量评价氚在结构材料和老龄贮氢材料内部的滞留量,用化学蚀刻法测定不锈钢内部氚浓度大小、分布情况及同位素交换后老龄贮氚铀床的氚滞留量。结果表明,贮氚13年的不锈钢样品中氚主要存在于样品内表面由表及里的120μm范围内,样品蚀刻深度110.6μm范围内,不锈钢的平均氚滞留量～9.37×10-4mmol/g,贮氚铀粉平均氚滞留量～4.16×10-5mmol/g。该方法对测量金属中微量氚有较高灵敏度,可检测金属中残余氚的滞留量。     

高温下He^＋辐照316L不锈钢时氦泡的形态及氦的俘获

用ＴＥＭ观察６００℃下氦离子辐照３１６Ｌ不锈钢中氦泡的形态及分布，发现氦浓度比较低时，氦泡优先在位错线上形成；随着氦浓度的增大，氦泡在基体中均匀分。在晶粒内及晶界处，拟泡都呈多面体形状，观察的晶界片不存在氦不民的优先生长现象。     

氚污染不锈钢、铜、铝金属干法去污研究

为了考察氚污染金属干法去污的去污效率,对氚污染不锈钢、铜和铝进行了紫外线、臭氧、加热及联合（紫外线、臭氧与加热）去污实验研究。研究结果表明：紫外线单独照射去污效率较差,加热可明显提高去污效率,500 ℃联合172 nm的紫外线去污4 h对不锈钢表面氚去污率可达99.2%;臭氧对铜有较好的去污效率,臭氧与加热（500 ℃）的组合对不锈钢、铝、铜的去污率均高于99.2%;高温（500 ℃）较低温（300 ℃）去污效率高;氚去污后金属放置30 d表面氚有所增加,主要是氚的扩散和渗透所致;氚污染不锈钢存在4种氚吸附态。     

高压氘氚气氛下不锈钢吸附氚的初步研究

本工作对于氚在不锈钢表面的吸附和解吸行为进行了初步研究.样品在n(D)∶n(T)=1∶1,230℃时,15 MPa下恒温8 h后,接着在27 MPa下恒温6 h的情况下进行了氚的吸附,测量了室温下和加热到1173 K时的解吸氚量和总吸附量.其结果如下:不锈钢的总吸附氚量是857.4 MBq·cm-2,不锈钢的解吸氚量是722.2 MBq·cm-2;在本实验的条件下,在室温和加热条件下,不锈钢所释放的氚中,化学成分主要是HTO和HT两部分,大部分以HT形式存在;不锈钢的自由氚占吸附总氚量的7.34%;不锈钢的热解吸谱存在三个解吸峰,其解吸温度分别为439、530和843K.     

不锈钢和铜吸氚及其干法去污

为了对不锈钢和无氧铜吸氚后氚在其内部的分布情况及除氚去污方法进行研究,对模拟吸氚及加热去污后的样品进行了酸蚀刻以考察氚在金属层中的分布情况;单独加热或加热结合通入空气、O3和紫外线(UV)进行去污,考察不同去污方式的去污效果。结果表明:金属在表层1μm内吸附了大量的氚,约占总量的42%;加热到500℃及联合去污不锈钢的最佳去污因子达到286,铜为150,通入气体在中温条件下对金属去污最有效,加热是金属去污最有效方式;氚热解吸形态分析表明氚污染不锈钢有4种吸附态。     

Fe-Al/Al2O3阻氚涂层热处理条件对HR-2不锈钢力学性能影响

采用室温力学拉伸试验、显微硬度测试、X射线衍射及组织观察等方法研究了“室温熔盐电镀铝+热处理+选择性氧化”工艺路线制备Fe-Al/Al₂O₃阻氚涂层热处理过程对HR-2奥氏体不锈钢力学性能及显微组织的影响。结果表明：经热处理后的HR-2不锈钢仍然保持奥氏体组织;980 ℃热处理180 min时抗拉强度为580.48 MPa,硬度值为177.92 HV,伸长率为79.43%,具有优异的塑韧性;700 ℃热处理150 h时抗拉强度为616.47 MPa,硬度值为213.34 HV,伸长率为63.32%;经热处理后的HR-2不锈钢基体力学性能变化不大。现行的涂层制备工艺对基体材料影响较小,满足微观结构与力学性能指标。     

Resistivity studies of interstitial helium mobility in niobium

The mobility of interstitial helium in Nb and Nb-O alloys was studied in the temperature range of 10–383 K using resistivity measurements. The helium was introduced by radioactive decay of solute tritium (~ 1 at%). At $\text{T < 100 K}$ the resistivity increased due to conversion of tritium trapped at oxygen interstitials to helium. The formation of helium caused a very significant resistance increase at room temperature and above. The results suggest that helium is mobile at temperatures above 295 K and that the precipitation of large helium bubbles occurs along grain boundaries. The mobile helium species may either be single interstitials or small helium clusters. The activation enthalpy for the diffusion of the mobile helium species was estimated to be about 55 kJ/mol (0.66 eV).     

Surface cracking on Σ3, Σ9 CSL and random grain boundaries in helium implanted 316L austenitic stainless steel

The relationship between surface cracking at grain boundaries and the grain boundary nature in helium implanted 316L austenitic stainless steel was investigated by in situ annealing in a high-voltage electron microscope, and by SEM and TEM observations. The nucleation and growth of helium bubbles at a random grain boundary was observed during annealing up to 973 K. After annealing, surface cracking was observed at the random grain boundaries and some coincidence site lattice (CSL) boundaries because of the formation and rupture of the helium bubbles at these grain boundaries. At the faceted CSL boundaries, surface cracking occurred only on one boundary facet plane. This indicates that the twin boundary and pure tilt Σ9 CSL boundary show the highest resistance to cracking because of their low boundary energies.     

Effect of injection temperature, 5% pre-strain and long time aging on the high-temperature mechanical properties of helium injected 316 stainless steel

The helium embrittlement of 316 stainless steel, helium injected to concentrations of 3 ~ 10 at ppm at 573 ± 50 or 1073 ± 20 K, was measured by tensile tests at 1023 K and was completely suppressed by the 5% pre-straining. This improved effect was lost by a post-injection again of 1000 h at 1123 K or 3000 h at 1023 K. It was concluded from the TEM observations that in the solution treated material helium bubbles were concentrated on the grain boundaries and caused embrittlement, but in the 5% pre-strained material helium bubbles nucleated on the dislocations and grew large enough to be unable to be dragged to the grain boundaries by the dislocations during the tensile test. The embrittlement after the long time aging was due to the gathering of the large helium bubbles at the σ-phase boundaries by a sweepout mechanism due to dislocation climb during the long time thermal recovery process.     

Impact of nuclear irradiation on helium bubble nucleation at interfaces in liquid metals coupled to permeation through stainless steels

The impact of nucleating gas bubbles in the form of a dispersed gas phase on hydrogen isotope permeation at interfaces between liquid metals, like LLE, and structural materials, like stainless steel, has been studied. Liquid metal to structural material interfaces involving surfaces, may lower the nucleation barrier promoting bubble nucleation at active sites. Hence, hydrogen isotope absorption into gas bubbles modelling and control at interfaces may have a capital importance regarding design, operation and safety.He bubbles as a permeation barrier principle is analysed showing a significant impact on hydrogen isotope permeation, which may have a significant effect on liquid metal systems, e.g., tritium extraction systems. Liquid metals like LLE under nuclear irradiation in, e.g., breeding blankets of a nuclear fusion reactor would generate tritium which is to be extracted and recirculated as fuel. At the same time that tritium is bred, helium is also generated and may precipitate in the form of nano bubbles.Phenomena modelling is exposed and implemented in openFROM^® CFD tool for 0D to 3D simulations. Results for a 1D case show the impact of a He dispersed phase of nano bubbles on hydrogen isotopes permeation at an interface. In addition, a simple permeator simulation, consisting in a straight 3D pipe is exposed showing the effect of a He dispersed gas phase on hydrogen isotope permeation through different stainless steels. Results show the permeation reduction as a function of the interface area covered by He bubbles.Our work highlights the effect of gas bubble nucleation at interfaces and the importance of controlling these phenomena in nuclear technology applications.     

金属氚化物中氦泡生长显微机制研究现状与发展趋势

氚是核聚变反应的关键核燃料,金属氚化物是国防领域及核聚变能源领域中的重要功能材料。氚衰变产生的氦原子及其演化过程严重影响金属氚化物的宏观性能,氦泡的形成与驻留又会影响金属氚化物的贮氚性能,金属氚化物中氦泡生长机制的研究是备受关注的重要科学问题。受限于氚的放射性和缺乏对氚与氦等轻元素原子的显微分析技术,氦泡生长模型的研究长期处于唯象理论阶段。近年来,随着电子显微分析技术的进步,提出了更加准确分析氦泡信息的新技术,氦泡生长显微机制研究取得了新的突破。本文将首先简要介绍金属氚化物中氦泡生长机制的主要理论与成果,然后介绍电子显微分析技术的发展及研究成果,最后针对氦泡生长显微机制的研究趋势做出展望。