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Effect of microstructure variation induced by processing on corrosion behavior of Zr-Sn-Nb alloy 加工引起的微观结构变化对 Zr-Sn-Nb 合金腐蚀行为的影响
IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Pub Date : 2024-09-19 DOI: 10.1016/j.jnucmat.2024.155418
Yuzhen Jia, Zongpei Wu, Xun Dai, Wei Yi

In order to investigate the effect of microstructure variation induced by processing on corrosion behavior of zirconium alloys, Zr-Sn-Nb alloy original plates were processed by rolling and annealing, and the microstructure and corrosion behavior of both original plates and processed plates were analyzed. It was found that after the original plates were processed, the recrystallized microstructure in original plates was transformed to stress-relieved microstructure in processed plates, with second phase particles ripening. When exposed to pure water and water containing H3BO3 and LiOH, the original plates have better corrosion property than the processed plates, and the corrosion transition of the processed plates happened earlier than that of the original plates. The grain structure differences of original plates and processed plates have two aspects of influence on oxide cracking and corrosion transition. Firstly, there were more defects in processed plates which results in smaller grains and larger grain boundary areas in oxide. Secondly, the strength of processed plates is higher, and this will lead to less stress accommodation of the growing oxide by plastic deformation of the matrix, and higher stress in oxide layer formed during the corrosion process. Both factors caused more cracks in the oxide layer of processed plates, leading to earlier corrosion transition and decreasing corrosion property. Second phase particles and their surroundings are susceptible to cracks during corrosion process, and may become the original source of cracks. However, second phase particle ripening was not closely related to decreasing corrosion property of processed plates.

为了研究加工引起的显微组织变化对锆合金腐蚀行为的影响,对 Zr-Sn-Nb 合金原始板材进行了轧制和退火加工,并分析了原始板材和加工板材的显微组织和腐蚀行为。结果发现,原始板材经过加工后,原始板材中的再结晶显微组织转变为加工板材中的应力释放显微组织,第二相颗粒发生熟化。在纯水和含 H3BO3、LiOH 的水中,原始板材的腐蚀性能优于加工板材,且加工板材的腐蚀转变早于原始板材。原始板和加工板的晶粒结构差异对氧化物开裂和腐蚀转变有两方面的影响。首先,加工板中的缺陷较多,导致氧化物中的晶粒较小,晶界区域较大。其次,加工板的强度较高,这将导致基体塑性变形对生长中的氧化物的应力容纳较小,而在腐蚀过程中形成的氧化层应力较大。这两个因素都会使加工板的氧化层出现更多裂纹,导致腐蚀转变提前,腐蚀性能降低。第二相颗粒及其周围环境容易在腐蚀过程中产生裂纹,并可能成为裂纹的原始来源。然而,第二相颗粒熟化与加工板腐蚀性能下降的关系并不密切。
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引用次数: 0
Experimental assessment of thermodynamic stability and nucleation of NiO in liquid lead-bismuth eutectic for MYRRHA 用于 MYRRHA 的液态铅铋共晶中氧化镍的热力学稳定性和成核的实验评估
IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Pub Date : 2024-09-18 DOI: 10.1016/j.jnucmat.2024.155404
Aleksandr Tsybanev , Alessandro Marino , Jun Lim , Kristof Gladinez , Nele Moelans
MYRRHA is an accelerator-driven system with a primary coolant of liquid lead-bismuth eutectic (LBE). Nickel, a major corrosion product released in LBE during normal operation, can potentially form oxides and intermetallic compounds with bismuth. This study focuses on the behavior of dissolved nickel and the conditions for nickel oxide (NiO) formation in LBE.
We first measured the dissolved oxygen concentration (DOC) at the NiO equilibrium from 225 to 500 °C across three levels of nickel concentration. These measurements showed a deviation from the trend expected from literature, particularly in the range of 325–400 °C. Based on the measurements, we proposed the activity coefficient of Ni in LBE within this temperature range. Secondly, we identified the conditions for NiO nucleation by cyclically varying the temperature of LBE at high nickel concentration and different DOC levels. Based on these observations, we concluded that NiO nucleation is unlikely under the MYRRHA operating conditions (200–400 °C, 10–7–10–6 wt.%).
MYRRHA 是一个加速器驱动系统,其主冷却剂为液态铅铋共晶(LBE)。镍是铅铋共晶液在正常运行期间释放的主要腐蚀产物,有可能与铋形成氧化物和金属间化合物。我们首先测量了 225 至 500 °C 三种镍浓度水平下镍氧化物平衡时的溶解氧浓度 (DOC)。这些测量结果显示与文献中预期的趋势存在偏差,尤其是在 325-400 °C 的范围内。根据测量结果,我们提出了该温度范围内镍在 LBE 中的活性系数。其次,我们通过循环改变高镍浓度和不同 DOC 水平下的 LBE 温度,确定了 NiO 成核的条件。根据这些观察结果,我们得出结论:在 MYRRHA 工作条件(200-400 °C,10-7-10-6 wt.%)下,不可能出现氧化镍成核现象。
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引用次数: 0
Quantitative phase-field simulation of Pu oxidation at low temperatures through a pragmatic strategy for coupling with thermodynamic and diffusion descriptions of stoichiometric compounds 通过与化学计量化合物的热力学和扩散描述耦合的实用战略,对低温下的钚氧化进行定量相场模拟
IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Pub Date : 2024-09-18 DOI: 10.1016/j.jnucmat.2024.155413
Sa Ma , Pengchuang Liu , Lijun Zhang
In this letter, we developed a pragmatic strategy for coupling the phase-field model with the thermodynamic/kinetic descriptions and applied it to quantitatively describe the complex oxidation process of Pu. The microstructure evolution of Pu during oxidation at 423 K and 473 K was carefully simulated, and the thickness curves of various oxides were successfully predicted, which can provide the theoretical support for the storage and protection of Pu related materials. Furthermore, it is anticipated that the pragmatic strategy is universally applicable for quantitative simulation of the complex oxidation process.
在这封信中,我们发展了一种将相场模型与热力学/动力学描述耦合的实用策略,并将其应用于定量描述钚的复杂氧化过程。我们仔细模拟了钚在 423 K 和 473 K 氧化过程中的微观结构演变,成功预测了各种氧化物的厚度曲线,为钚相关材料的储存和保护提供了理论支持。此外,预计该实用策略普遍适用于复杂氧化过程的定量模拟。
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引用次数: 0
Thermal corrosion behavior of Inconel 693, Hastelloy N and 310S in ceramic waste forming reactions 铬镍铁合金 693、哈氏合金 N 和 310S 在陶瓷废料成型反应中的热腐蚀行为
IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Pub Date : 2024-09-18 DOI: 10.1016/j.jnucmat.2024.155416
Zongyao Ge , Shengheng Tan , Yingju Li , Liangjin Bao , Xiaohui Feng , Tianyu Liu , Yuansheng Yang
The thermal corrosion behavior of Inconel 693, Hastelloy N, and 310S was investigated in the reaction environment of ceramic waste forming reactions. Due to the difference in Cr content and the effect of chlorides, the high Cr Inconel 693 and 310S alloys exhibit selective corrosion by Cr, while the low Cr Hastelloy N exhibits uniform corrosion and the volatilization of MoO3 caused high dimensional losses. The different behavior of the alloys in different corrosive environmental regions is also discussed. In the sintered product region, due to the encapsulation of the sintered product and the corrosion inhibiting role played by O2−, Hastelloy N alloy and 310S alloy experienced milder corrosion compared to alloy in the atmosphere region. And in the atmosphere region, the more abundant gas supply and the open environment caused Hastelloy N alloy and 310S alloy to experience more severe erosion. However, for Inconel 693 alloy, it formed a continuous spinel phase layer containing FeCr2O4 due to the higher partial pressure of O2 in the atmosphere region, resulting in more slight corrosion compared to the sintered product region.
研究了因科镍合金 693、哈氏合金 N 和 310S 在陶瓷废物成型反应环境中的热腐蚀行为。由于铬含量的不同和氯化物的影响,高铬 Inconel 693 和 310S 合金表现出铬的选择性腐蚀,而低铬 Hastelloy N 则表现出均匀腐蚀,MoO3 的挥发造成了较高的尺寸损失。此外,还讨论了合金在不同腐蚀环境区域的不同行为。在烧结产品区域,由于烧结产品的封装和 O2- 的缓蚀作用,哈氏合金 N 和 310S 的腐蚀比大气区域的合金要轻微。而在大气区,更充足的气体供应和开放的环境导致哈氏合金 N 和 310S 受到更严重的侵蚀。然而,对于 Inconel 693 合金而言,由于大气区域中的氧气分压较高,它形成了含有 FeCr2O4 的连续尖晶石相层,因此与烧结产品区域相比,腐蚀更为轻微。
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引用次数: 0
LBE corrosion behavior of helium pre-irradiated martensitic steel 氦预辐照马氏体钢的 LBE 腐蚀行为
IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Pub Date : 2024-09-18 DOI: 10.1016/j.jnucmat.2024.155405
Xudong Liu , Hongpeng Zhang , Yao Yang , Li Zhao , Ji Wang , Tielong Shen , Liangting Sun , Minghuan Cui , Tianji Peng , Xiaojing Li , Leli Chen , Rui Yu , Changping Qin , Yanze Tang , Wangsheng Tian , Xukai Fan , Zhiguang Wang , Cunfeng Yao
In the design of the spallation target of CiADS, T91 steel was selected for the most critical component, the beam window. A Si-modified martensitic steel (SIMP) has been currently developed, which has better corrosion resistance and is planning to replace T91 as a material of beam window in the future. In order to assess the effect of irradiation damage on the microstructure evolution and corrosion behavior of the SIMP, the pre-irradiated samples with irradiation doses from 5 × 1015 to 3 × 1017 He/cm2 exposed in static lead-bismuth eutectic (LBE) with saturated oxygen at 350 °C for 4000 h were investigated. Results show that pre-irradiation neither change the double-layer structure of the oxide layer nor significantly affect the corrosion rate. This may be due to the slow diffusion of elements at low temperatures, and the low irradiation dose not reaching the threshold for triggering accelerated corrosion.
在 CiADS 的溅射靶设计中,最关键的部件--束窗--选用了 T91 钢。目前已开发出一种具有更好耐腐蚀性能的硅改性马氏体钢(SIMP),并计划在未来取代 T91 作为束窗材料。为了评估辐照损伤对 SIMP 微观结构演变和腐蚀行为的影响,研究了在 350 °C 饱和氧静态铅铋共晶(LBE)中暴露 4000 小时的预辐照样品,辐照剂量为 5 × 1015 至 3 × 1017 He/cm2。结果表明,预辐照既不会改变氧化层的双层结构,也不会显著影响腐蚀速率。这可能是由于元素在低温下的扩散速度较慢,而且辐照剂量较低,没有达到引发加速腐蚀的临界值。
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引用次数: 0
How precisely are solute clusters in RPV steels characterized by atom probe experiments? 原子探针实验如何精确表征 RPV 钢中的溶质团块?
IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Pub Date : 2024-09-17 DOI: 10.1016/j.jnucmat.2024.155412
N. Castin , P. Klupś , M.J. Konstantinović , G. Bonny , M.I. Pascuet , M. Moody , L. Malerba
Atom probe tomography (APT) is a powerful microscopy technique to characterize nano-sized clusters of the alloying elements in the bulk of reactor pressure vessel (RPV) steels. These clusters are known to dominantly determine the evolution of mechanical properties under irradiation. The results are conventionally summarized as the overall number density N and the average diameter D of the solute clusters identified in the material. Here, we illustrate that these descriptors are intrinsically imprecise because they are steered by the parameters involved in the measurement and data processing, some of which are directly under the control of the operators, but some others not. Consequently, a direct comparison between data derived at different laboratories is compromised, and key trends such as the evolution with dose, are masked. This study relies on a state-of-the-art physical model for neutron irradiation in steels to make reliable estimates of the microstructure before the measurement is performed, which allows the prediction of the population of solute clusters that are not seen by APT. We mimic APT measurements from simulated microstructures, performing a detailed study of the effects of the parameters of the analysis. We show that the values of N and D reported in the scientific literature can be matched by the predictions of our theoretical model only if specific sets of parameters are used for each laboratory that issued the measurements. We also show that if, on the contrary, all studied cases are analyzed in a consistent way, the scatter of N and D values is reduced. Specifically, we find that the average diameter D is nearly a constant value with dose, independently of the material's chemical compositions, while N increases with dose, but is also influenced by other variables. The approach we developed and used proves to have added value as complement to APT experiments in reactor pressure vessel steels.
原子探针层析技术(APT)是一种功能强大的显微镜技术,可用于表征反应堆压力容器(RPV)钢体中合金元素的纳米级团簇。众所周知,这些团簇主要决定了辐照下机械性能的演变。研究结果通常总结为材料中已识别溶质团簇的总数量密度 N 和平均直径 D。在这里,我们要说明的是,这些描述符本质上是不精确的,因为它们受到测量和数据处理过程中的参数的影响,其中一些参数直接受操作人员的控制,而另一些参数则不受控制。因此,对不同实验室得出的数据进行直接比较会受到影响,而且关键趋势(如随剂量变化的趋势)也会被掩盖。本研究利用最先进的钢材中子辐照物理模型,在进行测量前对微观结构进行可靠的估计,从而预测 APT 无法看到的溶质团簇群。我们通过模拟微观结构模拟 APT 测量,对分析参数的影响进行了详细研究。我们的研究表明,只有在每个进行测量的实验室都使用特定参数集的情况下,科学文献中报告的 N 值和 D 值才能与我们理论模型的预测值相匹配。我们还表明,相反,如果以一致的方式分析所有研究案例,N 值和 D 值的散布就会减少。具体来说,我们发现平均直径 D 几乎是剂量的恒定值,与材料的化学成分无关,而 N 则随剂量增加,但也受其他变量的影响。事实证明,我们开发和使用的方法对反应堆压力容器钢的 APT 实验具有补充价值。
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引用次数: 0
Exploring constituent redistribution in irradiated U-19Pu-14Zr fuel via electron probe microanalysis 通过电子探针显微分析探索辐照 U-19Pu-14Zr 燃料中的成分再分布
IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Pub Date : 2024-09-17 DOI: 10.1016/j.jnucmat.2024.155411
Karen E. Wright , Lindsey Lecrivain , Cortney Pincock , Magen Coleman , Pamela Wiscaver , Beau Barker , Luiza Gimenes Rodrigues Albuquerque , Luca Capriotti , Assel Aitkaliyeva
The phenomena of constituent redistribution, wherein a previously homogeneous metallic fuel forms discrete, radially concentric compositional zones upon irradiation was investigated by examining an irradiated U-19Pu-14Zr fuel (where numbers represent wt. %) with a burnup of 11.5 at.% with electron probe microanalysis (EPMA) and quadruple inductively coupled plasma mass spectroscopy (Q-ICP-MS).
EPMA-generated U, Pu, and Zr compositional data obtained from a diameter traverse of the sample was converted to mass and was used to: 1) compare the overall fuel element analysis results between the two methods, 2) determine the number of compositionally distinct zones forming as a result of constituent redistribution; and 3) quantify the post-irradiation loss or gain of U, Pu, and Zr atoms in each distinct compositional zone.
Weight percent concentrations of U, Pu, and Zr for the overall cross section compare favorably between the two analytical methods, suggesting that the spatially resolved EPMA analysis complements bulk chemical analysis.
Among the four identified compositional zones, post-irradiation quantification of U, Pu, and Zr elemental atom content changes shows that the quantity of U atoms lost from the innermost zone is slightly less than the quantity of U atoms gained by the middle two zones, and the quantity of Zr atoms lost from the high-U third zone is slightly less than is gained by the two innermost zones. Pu is lost from all four zones, although the innermost zone and the high-U third zone lose a significantly higher percentage (> 22 %) of their initial Pu atoms than the other two zones. For all three elements, EPMA cannot distinguish between atoms lost due to transport to a different zone from atoms lost due to nuclear processes; however, the insight gained from using this process can be used to experiment with new modeling techniques to predict constituent redistribution in U-Pu-Zr fuels.
通过使用电子探针显微分析(EPMA)和四重电感耦合等离子体质谱(Q-ICP-MS)对燃烧度为 11.5 at.%、经过辐照的 U-19Pu-14Zr 燃料(数字代表重量百分比)进行检测,研究了成分再分布现象,即之前均匀的金属燃料在辐照后形成离散的、径向同心的成分区。电子探针显微分析(EPMA)和四重电感耦合等离子体质谱(Q-ICP-MS)对燃烧度为 11.5 at.% 的辐照铀-19Pu-14Zr 燃料(数字代表重量百分比)进行了研究:1) 比较两种方法的总体燃料元素分析结果;2) 确定由于成分再分布而形成的不同成分区的数量;3) 量化每个不同成分区中辐照后铀、钚和锆原子的损耗或增益。在已确定的四个成分区中,对辐照后铀、钚和锆元素原子含量变化的定量分析表明,最内层区损失的铀原子数量略少于中间两个区获得的铀原子数量,而高铀第三区损失的锆原子数量略少于最内层两个区获得的锆原子数量。所有四个区都损失了钚,但最内区和高铀第三区损失的钚原子占其初始钚原子的百分比(22%)明显高于其他两个区。对于所有这三种元素,EPMA 无法区分因迁移到不同区域而损失的原子和因核过程而损失的原子;不过,利用这一过程获得的洞察力可用于试验新的建模技术,以预测铀-钚-锌燃料中的成分再分布。
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引用次数: 0
Effects of irradiation on interfacial strength and microstructure of double-layer mullite and alumina coating on SiC 辐照对碳化硅双层莫来石和氧化铝涂层界面强度和微观结构的影响
IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Pub Date : 2024-09-15 DOI: 10.1016/j.jnucmat.2024.155410
Taichi Miyagishi , Sosuke Kondo , Hirokazu Katsui , Kiyohiro Yabuuchi , Ryutaro Usukawa , Yasuyuki Ogino , Hao Yu , Ryuta Kasada
Silicon carbide (SiC) ceramics hold great potential for use in nuclear-reactor components due to characteristics such as high-temperature strength and low activation. Despite their resistance against corrosion in harsh environments, they suffer elevated corrosion rates under particle irradiation. Thin anti-corrosion coatings, such as mullite bond layers and alumina top layers, are essential to enhance the irradiation stability of SiC. The objective of this study was to evaluate the irradiation stability of a double-layer coating developed to enhance the corrosion resistance of SiC in nuclear applications. The coating, which comprised a mullite bond layer and an alumina top layer, was applied to a SiC substrate using laser chemical vapor deposition. Irradiation experiments were conducted at 300 °C with 5.1-MeV Si ions up to 10 displacements per atom. To assess the interfacial strength, a novel testing method, called the double-notch shear compression testing method, was developed based on ASTM standards and was implemented using a nanoindenter. This approach enabled precise measurements of the mechanical integrity at the interfaces of the coating under irradiation. The results showed an increase in the interfacial strength at the SiC/mullite and alumina/mullite interfaces with irradiation. Microstructural analysis of the fracture surface through scanning electron microscopy–energy-dispersive X-ray spectroscopy revealed that cracks propagated within the mullite layer, indicating the presence of mullite on the fracture surface. Transmission electron microscopy (TEM) images indicated that a 2-µm-thick transition layer existed at the SiC/mullite interface but not at the alumina/mullite interface. The TEM–electron energy loss spectroscopy suggested that the Al-O bonding structures in the transition layer were changed from tetrahedral (AlO4) to octahedral (AlO6) through irradiation, and this structural transition may directly affect the strength.
碳化硅(SiC)陶瓷具有高温强度和低活化等特性,因此在核反应堆部件中具有巨大的应用潜力。尽管碳化硅陶瓷在恶劣环境中具有抗腐蚀性,但在粒子辐照条件下,其腐蚀率会升高。薄防腐蚀涂层(如莫来石结合层和氧化铝面层)对于提高碳化硅的辐照稳定性至关重要。本研究的目的是评估一种双层涂层的辐照稳定性,该涂层是为提高碳化硅在核应用中的耐腐蚀性而开发的。该涂层由莫来石结合层和氧化铝表层组成,采用激光化学气相沉积方法涂覆在碳化硅基底上。辐照实验是在 300 °C 温度下用 5.1-MeV Si 离子进行的,每个原子的位移高达 10 次。为了评估界面强度,根据 ASTM 标准开发了一种名为 "双缺口剪切压缩测试法 "的新型测试方法,并使用纳米压头进行了实施。这种方法可以精确测量辐照下涂层界面的机械完整性。结果表明,随着辐照的进行,SiC/莫来石和氧化铝/莫来石界面的界面强度有所增加。通过扫描电子显微镜-能量色散 X 射线光谱法对断裂表面进行的微观结构分析表明,裂纹在莫来石层内传播,表明断裂表面存在莫来石。透射电子显微镜(TEM)图像显示,在碳化硅/莫来石界面上存在 2 微米厚的过渡层,而在氧化铝/莫来石界面上则没有。透射电子显微镜-电子能量损失光谱表明,通过辐照,过渡层中的 Al-O 键合结构从四面体(AlO4)变为八面体(AlO6),这种结构转变可能直接影响强度。
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引用次数: 0
Interfacial evolution in Cr/Mo-coated Zr alloys near the Mo-Zr eutectoid temperature 钼-锆共晶温度附近铬/钼涂层锆合金的界面演变
IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Pub Date : 2024-09-14 DOI: 10.1016/j.jnucmat.2024.155406
Bo Li , Jingjie Shen , Zongda Yang , Huilong Yang , Sho Kano , Hiroaki Abe

This study investigates the interfacial evolution of Cr/Mo-coated Zr alloys near the Mo-Zr eutectoid temperature, from the viewpoints of microstructure and chemical composition and with the joint application of XRD, TEM and EDS analyses. The experimental findings highlight significant changes in microstructure and diffusion behavior associated with the Mo-Zr eutectoid reaction. In the as-fabricated specimen, it is noted that introducing a Mo-intermediate layer results in the formation of an amorphous Cr layer at the Cr/Mo interface. In the case of the annealing temperature below the Mo-Zr eutectoid reaction, Mo interlayer effectively impedes the diffusion between Cr and Zr, thereby suppressing the formation of intermetallic compounds. However, the diffusion barrier function of Mo interlayer deteriorates when the temperature exceeds the eutectoid point, with the presence of four distinct diffusion zones, including α-Zr, β-Zr, the intermetallic compound Zr(Mo,Cr,Fe)₂, and the Mo layer containing fine Zr(Mo,Cr,Fe)2 particles. These findings underscore the critical role of Mo-interlayer in influencing the structural stability and intermetallic compound formation in Cr/Mo-coated Zr alloys, not only at the temperature regime around the eutectic reaction, but also at the temperature regime around the eutectoid reaction, which is of great necessity for the practical applications of accident tolerant fuel cladding under high temperature environment.

本研究从微观结构和化学成分的角度出发,联合应用 XRD、TEM 和 EDS 分析,研究了在 Mo-Zr 共晶温度附近 Cr/Mo 涂层 Zr 合金的界面演变。实验结果凸显了与 Mo-Zr 共晶反应相关的微观结构和扩散行为的显著变化。在原样试样中,引入 Mo 中间层会在 Cr/Mo 界面形成无定形 Cr 层。在退火温度低于 Mo-Zr 共晶反应时,Mo 中间层会有效阻碍 Cr 和 Zr 之间的扩散,从而抑制金属间化合物的形成。然而,当温度超过共晶点时,Mo 夹层的扩散阻隔功能就会恶化,出现四个不同的扩散区,包括 α-Zr、β-Zr、金属间化合物 Zr(Mo,Cr,Fe)₂ 和含有细小 Zr(Mo,Cr,Fe)2 颗粒的 Mo 层。这些发现强调了钼中间层在影响铬/钼包覆 Zr 合金的结构稳定性和金属间化合物形成方面的关键作用,不仅在共晶反应附近的温度体系中,而且在类共晶反应附近的温度体系中也是如此。
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引用次数: 0
Effect of cold work level on the crack propagation behaviour of 316LN stainless steel in high-temperature pressurized water 冷加工水平对 316LN 不锈钢在高温加压水中裂纹扩展行为的影响
IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Pub Date : 2024-09-14 DOI: 10.1016/j.jnucmat.2024.155403
Wei Sun , Bin Wu , Hongliang Ming , Jianqiu Wang , En-Hou Han

We investigated the microstructure, mechanical properties, and stress corrosion cracking (SCC) propagation behaviour of 316LN austenitic stainless steel with various cold work (CW) levels. CW increased the crack growth rate of 316LN. The stress corrosion crack growth rate (SCCGR) for 316LN with 5% CW was approximately 6.52% higher than that of the solution-annealed state; 10%, 20%, and 30% CW resulted in 1.20, 3.18, and 6.10 times higher SCCGRs, respectively. A larger residual strain and proliferation of slip bands via cold deformation augmented the SCCGR. The SCC propagation mechanism of 316LN changed with increasing CW levels owing to slip bands.

我们研究了不同冷加工(CW)水平下 316LN 奥氏体不锈钢的微观结构、机械性能和应力腐蚀开裂(SCC)扩展行为。冷加工提高了 316LN 的裂纹生长率。5% CW 的 316LN 的应力腐蚀裂纹生长率(SCCGR)比固溶退火状态高出约 6.52%;10%、20% 和 30% CW 的 SCCGR 分别高出 1.20、3.18 和 6.10 倍。通过冷变形产生的较大残余应变和滑移带的扩散提高了 SCCGR。由于滑移带的存在,316LN 的 SCC 传播机制随着 CW 水平的增加而改变。
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Journal of Nuclear Materials
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