Journal of Nuclear Materials最新文献_第7页

Molecular dynamics study on the effect of interstitial hydrogen clusters on the slip of edge dislocation in tungsten 间隙氢团簇对钨中边位错滑移影响的分子动力学研究

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials

Pub Date : 2026-03-01 Epub Date: 2026-01-09 DOI: 10.1016/j.jnucmat.2026.156448

Yifan Liu , Ke Xu , Zhiye Tang , Chenxin Yan , Shuo Jin , Linyun Liang , Hong-Bo Zhou , Guang-Hong Lu

Interstitial hydrogen (H) clusters with rock salt structure exhibit energy stability in tungsten (W) and play a crucial role in enhancing its hardness. However, the underlying physical mechanisms and the specific hardening behavior remain unclear. To this end, we systematically investigate the effect of the H cluster on the slip behavior of an 1/2 [111] (

1 \bar{1} 0

) edge dislocation in W by using the molecular dynamics method. We first study the slip of the edge dislocation in the absence of the H cluster, which reveals typical phonon drag control characteristics. Based on this, a slip drag coefficient B(T) is obtained, enabling accurate prediction of the dislocation mobility under various temperatures and stresses. In the presence of H clusters, the hardening effect in W is significantly enhanced. Notably, the geometric parameters of the H cluster, i.e., height and diameter, exert significant regulatory influence on the slip behavior of the edge dislocation through a quantitative correlation. Furthermore, the critical resolved shear stress (CRSS) displays a slight dependence on temperature within the range of 100 K-800 K, indicating that the dislocation motion is primarily governed by the geometry of the H cluster. These results provide new insights into the mechanisms of H-induced irradiation hardening in W, offering valuable data to support the development of high-performance W-based materials with enhanced irradiation resistance and long-term service stability.

具有岩盐结构的间隙氢(H)团簇在钨(W)中表现出能量稳定性，对提高钨的硬度起着至关重要的作用。然而，潜在的物理机制和具体的硬化行为仍不清楚。为此，我们采用分子动力学方法系统地研究了H簇对W中1/2[111]（11¯0）边位错滑移行为的影响。我们首先研究了在没有H团簇的情况下，边缘位错的滑移，这揭示了典型的声子阻力控制特性。在此基础上，得到了滑移阻力系数B(T)，可以准确预测在不同温度和应力下的位错迁移率。当H团簇存在时，W中的硬化效果显著增强。值得注意的是，H簇的几何参数，即高度和直径，通过定量关联对边缘位错的滑移行为有显著的调节影响。此外，在100 K-800 K范围内，临界分解剪应力（CRSS）对温度有轻微的依赖，表明位错运动主要受H团簇几何形状的控制。这些结果为氢致W辐照硬化机理提供了新的见解，为开发具有增强辐照耐受性和长期使用稳定性的高性能W基材料提供了有价值的数据。

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引用次数: 0

Influence of defect sink strength on dislocation loop and helium bubble evolution in low-alloy steel under in-situ He irradiation and annealing 原位He辐照退火低合金钢缺陷沉降强度对位错环和氦泡演化的影响

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials

Pub Date : 2026-03-01 Epub Date: 2026-01-13 DOI: 10.1016/j.jnucmat.2026.156461

Jiyong Huang , Hucheng Yu , Yifan Ding , Xiangbing Liu , Ziqi Cao , Runzhong Wang , Wenqing Jia , Sheng Fan , Guang Ran

Understanding the formation and evolution of irradiation-induced defects under different effective sink strengths is essential for designing radiation-resistant structural materials in advanced nuclear systems. In this study, in situ He ion irradiation experiments were conducted at 450 °C on two regions of low-alloy steel materials with distinct sink strengths characterized by variations in dislocation density and precipitate distribution. In situ TEM observations revealed the formation and evolution behaviors of dislocation loops and helium bubbles during irradiation and subsequent annealing at 700 and 750 °C. Regions with higher sink strength exhibited lower dislocation loop density, smaller loop size, and a reduced fraction of a < 100> loops, indicating enhanced point-defect recombination and suppressed loop nucleation and growth. During irradiation, helium bubbles in the low-sink region were larger and non-spherical, while those in the high-sink region were finer and denser. Upon annealing, bubble size reversal occurred: bubbles in the high-sink region grew rapidly at later stages. At the final annealing stage, bubbles in the high-sink region were largely pinned, whereas smaller bubbles in the low-sink region exhibited thermally driven migration. These findings elucidate the critical role of effective sink strength in defect evolution and provide experimental insights for the microstructural design of radiation-resistant materials.

了解不同有效汇强度下辐照缺陷的形成和演变，对于设计先进核系统中抗辐射结构材料至关重要。在本研究中，在450°C下，对两个低合金钢材料进行了原位He离子辐照实验，这两个区域具有不同的汇强度，其特征是位错密度和沉淀分布的变化。原位TEM观察揭示了700℃和750℃辐照和后续退火过程中位错环和氦泡的形成和演化行为。沉降强度高的区域，位错环密度低，环尺寸小，< 100>；环的比例减少，表明点缺陷复合增强，环形核和生长受到抑制。辐照过程中，低汇区氦泡较大且呈非球形，而高汇区氦泡较小且密度较大。退火后，气泡尺寸发生逆转，高沉区气泡在后期迅速增长。在最后的退火阶段，高汇区的气泡大部分被钉住，而低汇区的小气泡则表现出热驱动迁移。这些发现阐明了有效吸收强度在缺陷演变中的关键作用，并为抗辐射材料的微结构设计提供了实验见解。

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引用次数: 0

Creep properties of solution-annealed 316H stainless steel made by laser-powder directed energy deposition additive manufacturing 激光粉末定向能沉积增材制造316H不锈钢固溶退火的蠕变性能

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials

Pub Date : 2026-03-01 Epub Date: 2026-01-07 DOI: 10.1016/j.jnucmat.2026.156444

John Snitzer , Benjamin Sutton , John Shingledecker , Xiaoyuan Lou

This work examines the high-temperature creep response of solution-annealed additively manufactured (AM) 316H stainless steel (SS) produced by laser-powder directed energy deposition (LP-DED) and support the efforts towards using AM for advanced nuclear applications. The work focused on the effects of laser power and build direction on creep properties. Creep testing was conducted at 650 °C at varying stresses from 130 to 200 MPa to ensure that dislocation climb-dominated creep was the primary mechanism. Solution annealing removed the as-built chemical segregation and cellular structures, forming a heterogeneous, partially recrystallized grain structure with subgrain structures pinned by oxide particles. Despite solution annealing, the laser power and build direction significantly influenced the microstructure resulting in AM specimens exhibiting higher minimum creep rates and lower rupture lives compared to wrought 316H tested in this work; however, the AM specimens remained within the scatterband of an existing wrought 316H database. The build direction significantly impacted the creep ductility, where the horizontally built specimens exhibited reduced creep ductility compared to vertically built and wrought specimens, attributed to the grain boundaries being primarily oriented perpendicular to the loading direction. Creep cavitation was observed primarily along grain boundaries near Cr₂₃C₆ and η-nitride precipitates. Intragranular precipitates were also observed in AM specimens but, due to the very low area density, had a limited effect on creep behavior. Power law analysis confirmed dislocation climb was the dominant creep mechanism in all specimens with exponents ranging from 6.1 to 6.9 for AM and 8.4 for wrought. Creep life analysis, conducted using Larson-Miller and Monkman-Grant methods, revealed processing variability induced varying creep life; however, the AM-produced material again fell within or higher than the wrought scatterband. Overall, the results indicate that solution-annealed, DED AM 316H SS can achieve creep performance consistent with wrought alloys, supporting its potential consideration for high-temperature structural applications.

这项工作研究了激光粉末定向能沉积（LP-DED）生产的溶液退火增材制造（AM） 316H不锈钢（SS）的高温蠕变响应，并支持将AM用于先进核应用的努力。研究了激光功率和构筑方向对材料蠕变性能的影响。在650℃下，在130 ~ 200 MPa的不同应力下进行蠕变试验，以确保位错爬升为主的蠕变是主要机制。固溶退火去除了原有的化学偏析和胞状结构，形成了非均质、部分再结晶的晶粒结构和由氧化物颗粒固定的亚晶粒结构。尽管溶液退火，激光功率和构建方向显著影响AM试样的微观结构，导致AM试样表现出更高的最小蠕变速率和更低的断裂寿命，与本工作中测试的变形316H相比；然而，AM样品仍然在现有的锻造316H数据库的散射带内。构建方向对蠕变延展性有显著影响，水平构建的试件与垂直构建和变形的试件相比，蠕变延展性降低，这是由于晶界主要垂直于加载方向。蠕变空化主要沿晶界观察到Cr23C6和η-氮化物析出。在AM试样中也观察到晶内析出，但由于极低的面积密度，对蠕变行为的影响有限。幂律分析证实位错爬升是蠕变的主要机制，AM的指数为6.1 ~ 6.9，锻造的指数为8.4。使用Larson-Miller和Monkman-Grant方法进行的蠕变寿命分析显示，加工变异性会导致蠕变寿命的变化；然而，am生产的材料再次落在或高于变形散射带。总体而言，结果表明，固溶退火的DED AM 316H SS可以获得与变形合金一致的蠕变性能，支持其在高温结构应用中的潜在考虑。

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引用次数: 0

In – situ chlorination of simulated fission products from light water reactor fuel using ZrCl4 使用ZrCl4对轻水反应堆燃料模拟裂变产物进行原位氯化

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials

Pub Date : 2026-03-01 Epub Date: 2025-12-29 DOI: 10.1016/j.jnucmat.2025.156418

Diallo Barnes, Courtney Eckley, Mary Cernyar, Michael F. Simpson

To develop a process for chlorinating spent nuclear fuel (SNF) from light water reactors and dissolving it into a molten salt, the reactivity of several surrogate fission products (SFPs) with NiCl₂ and ZrCl₄ in molten LiCl – KCl was tested. ZrCl₄ was created in-situ by reacting NiCl₂ and Zr metal in the molten salt. Powders of SrO, La₂O₃, CeO₂, Cs₂O, and a Mo metal rod were all immersed in eutectic LiCl – KCl with initially 8.9 wt% NiCl₂, likely exceeding the solubility limit. Salt samples were collected at several time intervals over 24 h and analyzed via inductively coupled plasma mass spectrometry (ICP – MS). NiCl₂ did not directly react with any of the SFPs, but in situ formed ZrCl₄ was reactive towards all the oxides. The Mo metal rod was virtually inert towards reaction with both NiCl₂ and ZrCl₄. Experiments were run at 773 or 873 K with or without stirring condition. Conversion of SrO, CeO₂, and La₂O₃ to soluble chlorides ranged from 87 – 93 %, while Cs₂O conversion was only 64 % on average. Some of the Ni metal by-product plated onto the Mo rod, which was unreactive towards chlorination. A solid containing Ni and ZrO₂ settled to the bottom of the crucible.

为了开发一种将轻水反应堆中的乏核燃料（SNF）氯化并溶解到熔盐中的工艺，测试了几种替代裂变产物（SFPs）与NiCl2和ZrCl4在熔融LiCl - KCl中的反应性。通过NiCl2和金属Zr在熔盐中原位反应生成ZrCl4。SrO、La2O3、CeO2、Cs2O粉末和Mo金属棒均浸在共晶LiCl - KCl中，初始NiCl2含量为8.9 wt%，可能超过了溶解度极限。在24 h的时间间隔内收集盐样品，并通过电感耦合等离子体质谱（ICP - MS）进行分析。NiCl2不与任何一种SFPs直接反应，但原位形成的ZrCl4对所有氧化物都有反应。Mo金属棒对NiCl2和ZrCl4的反应几乎是惰性的。实验温度分别为773、873 K，有或无搅拌条件。SrO、CeO2和La2O3对可溶性氯化物的转化率为87% ~ 93%，而Cs2O的平均转化率仅为64%。部分镍金属副产物镀在钼棒上，对氯化反应无反应。含有Ni和ZrO2的固体沉降到坩埚的底部。

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引用次数: 0

Mechanical properties and microstructure of CHSN01 conductor jacket under long-term cryogenic service in future fusion reactors CHSN01导体夹套在未来核聚变反应堆长期低温运行下的力学性能和显微组织

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials

Pub Date : 2026-03-01 Epub Date: 2026-01-20 DOI: 10.1016/j.jnucmat.2026.156463

Weijun Wang , Xinlan Ye , Baozhu Zhang , Yifei Wu , Huihui Zhi , Zhengping Tu , Xiaogang Shen , Jinggang Qin , Jiangang Li

The CHSN01 (formerly N50H) austenitic stainless-steel conductor jacket developed for China's future fusion reactor exhibits excellent strength and toughness with a yield strength exceeding 1500 MPa at -269°C, approximately 40% higher than that of the 316LN jacket used in ITER. However, the jacket material must also provide excellent safety performance under ongoing exposure to liquid He temperatures, but the effects of long-term cryogenic exposure on the microstructure and properties of CHSN01 remain unknown. Therefore, this study experimentally simulated the actual preparation and service conditions of the CHSN01 jacket to support its application in fusion reactors. First, the effects of different durations of immersion in liquid He dewar on the mechanical performance and microstructure of the material were characterized by tensile testing, scanning electron microscopy, transmission electron microscopy, X-ray diffraction, and electron backscatter diffraction. Next, the evolution of the material microstructure was studied under various strain conditions to reveal the resulting strengthening and toughening mechanisms. Finally, the feasibility of employing CHSN01 as a cryogenically resistant structural material capable of withstanding the high magnetic fields in next-generation fusion reactors was confirmed.

为中国未来核聚变反应堆开发的CHSN01（原N50H）奥氏体不锈钢导体夹套具有优异的强度和韧性，在-269°C时屈服强度超过1500 MPa，比ITER中使用的316LN夹套高约40%。然而，在持续暴露于液态He温度下，护套材料还必须提供出色的安全性能，但长期低温暴露对CHSN01的微观结构和性能的影响尚不清楚。因此，本研究通过实验模拟CHSN01夹套的实际制备和使用条件，为其在聚变反应堆中的应用提供支持。首先，通过拉伸测试、扫描电子显微镜、透射电子显微镜、x射线衍射和电子背散射衍射表征了不同浸泡时间对材料力学性能和微观结构的影响。其次，研究了不同应变条件下材料微观结构的演变，揭示了由此产生的强化和增韧机制。最后，验证了CHSN01作为抗低温结构材料在下一代核聚变反应堆中抗高磁场的可行性。

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引用次数: 0

Exploring iodide-mediated corrosion of NiCr20 alloys NiCr20合金的碘化物介质腐蚀研究

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials

Pub Date : 2026-03-01 Epub Date: 2025-12-25 DOI: 10.1016/j.jnucmat.2025.156402

Insung Han , Alejandro Ramos Ballesteros , Kim Kisslinger , Simerjeet K. Gill

A combined approach of microstructural characterization and thermodynamic calculations was employed to investigate the corrosion at alloy-salt interface of model Ni-based alloy (NiCr₂₀) and molten iodide salt system (LiI-KI). In iodide salt system, the corrosion of the NiCr₂₀ alloy is primarily driven by the selective dissolution of Cr, facilitated by grain boundary attack, which results in intergranular corrosion and the subsequent formation of pore-salt network. Additionally, the preferential formation of a Cr oxide surface film at the alloy-salt interface and salt filled void formation in the NiCr₂₀ alloy in molten LiI-KI salt system is examined and discussed. Understanding the corrosivity of iodide salts that can potentially exist as fission products or serve as surrogate molten salts is critical for assessing material degradation in molten salt reactors.

采用显微组织表征和热力学计算相结合的方法研究了模型镍基合金（NiCr20）和熔融碘化物盐体系（LiI-KI）在合金-盐界面的腐蚀。在碘化物盐体系中，NiCr20合金的腐蚀主要是由Cr的选择性溶解驱动的，晶界攻击促进了Cr的选择性溶解，导致晶间腐蚀并形成孔盐网络。此外，研究并讨论了熔融li - ki盐体系中NiCr20合金在合金-盐界面上优先形成氧化铬表面膜和盐填充空洞的现象。了解可能作为裂变产物存在或作为替代熔盐的碘盐的腐蚀性对于评估熔盐反应堆中的材料降解至关重要。

引用次数: 0

Investigations of size effect and normalization models for tensile deformation of A508-III steel miniature specimens A508-III钢微缩试样拉伸变形尺寸效应及归一化模型研究

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials

Pub Date : 2026-03-01 Epub Date: 2026-01-08 DOI: 10.1016/j.jnucmat.2026.156446

Cong Chen , Qi Zhang , Shengmin Xin , Wanhuan Yang , Junwan Li , Weihua Zhong , Guangsheng Ning

The miniature specimens with different grain sizes and thicknesses were prepared by changing the heat treatment temperature of A508-III steel. The tensile test of miniature specimens at room temperature was carried out, and the mechanism of tensile size effect was analyzed. The results indicate that variations in thickness and grain size lead to a significant size effect in tensile properties. By introducing an influence parameter λ comprehensively characterizing the grain and characteristic size effects of miniature specimen, the Swift mechanical constitutive model considering the size effect is established. To improve the damage model for miniature specimens, the ductile damage evolution parameter of miniature specimen is determined by the finite element aided testing (FAT) method. Based on the established mechanical constitutive model and ductile damage model, the load-displacement curve of the miniature specimen obtained through finite element analysis has an average error of less than 5% compared to the experimental test results. The tensile mechanical properties of miniature specimens are predicted by finite element method, and the normalized models of yield and tensile strength are constructed.

通过改变A508-III钢的热处理温度，制备了不同晶粒尺寸和厚度的微型试样。对微缩试样进行了室温拉伸试验，分析了拉伸尺寸效应的机理。结果表明，厚度和晶粒尺寸的变化对拉伸性能有显著的尺寸效应。通过引入综合表征微观试样晶粒效应和特征尺寸效应的影响参数λ，建立了考虑尺寸效应的Swift力学本构模型。为了完善微型试件的损伤模型，采用有限元辅助试验（FAT）方法确定了微型试件的延性损伤演化参数。基于建立的力学本构模型和延性损伤模型，通过有限元分析得到的微型试件载荷-位移曲线与试验试验结果的平均误差小于5%。采用有限元法预测了微型试样的拉伸力学性能，建立了屈服和抗拉强度的归一化模型。

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引用次数: 0

Effect of Al content and a Cr-N diffusion barrier on the high-temperature steam oxidation of FeCrAl coatings on Zry-4 Al含量和Cr-N扩散屏障对Zry-4表面feral涂层高温蒸汽氧化的影响

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials

Pub Date : 2026-03-01 Epub Date: 2025-12-29 DOI: 10.1016/j.jnucmat.2025.156422

Haiyan Liao , Xiaohan Deng , Weijiu Huang , Haibo Ruan , Shuai Lyu , Yuan Niu , Xiangkong Xu , Yongyao Su , Junjun Wang

This study systematically investigates the effects of Al content (3, 5, and 7 wt%) and a Cr-N diffusion barrier on the high-temperature steam oxidation performance of magnetron-sputtered FeCrAl coatings deposited on Zry-4. The tests were conducted at 1200 °C under simulated loss of coolant accident (LOCA) conditions in a steam environment. Results reveal that a minimum Al content of 5 wt% is required to form a continuous and dense Al₂O₃ layer, which significantly improves oxidation resistance. The Cr-N interlayer effectively suppressed the interdiffusion of Zr and Fe by promoting the in-situ formation of a continuous Zr(Fe,Cr)₂ Laves phase barrier during oxidation. This barrier inhibited the development of low-melting-point Fe-Zr eutectic phases, thereby enhancing interfacial stability. Compared with a pure Cr interlayer, the Cr-N barrier demonstrated superior performance in mitigating interdiffusion and improving coating durability. These findings highlight the critical roles of Al content and the Cr-N interlayer in optimizing FeCrAl coatings for accident-tolerant fuel (ATF) claddings, offering essential insights for designing zirconium alloy coatings with superior oxidation resistance and reliability under extreme conditions.

本研究系统地研究了Al含量（3、5、7 wt%）和Cr-N扩散阻挡层对Zry-4表面磁控溅射feral涂层高温蒸汽氧化性能的影响。试验在1200°C的温度下进行，在蒸汽环境中模拟冷却剂损失事故（LOCA）条件下进行。结果表明，当Al含量最低为5 wt%时，可以形成连续致密的Al2O3层，显著提高了抗氧化性能。Cr- n中间层通过促进氧化过程中原位形成连续的Zr(Fe,Cr)2 Laves相垒，有效抑制了Zr和Fe的相互扩散。这种势垒抑制了低熔点Fe-Zr共晶相的发展，从而提高了界面的稳定性。与纯Cr中间层相比，Cr- n势垒层在减缓相互扩散和提高涂层耐久性方面表现出更优异的性能。这些发现强调了Al含量和Cr-N中间层在优化耐事故燃料（ATF）包覆层的FeCrAl涂层中的关键作用，为设计在极端条件下具有优异抗氧化性和可靠性的锆合金涂层提供了重要见解。

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引用次数: 0

Spatially heterogeneous evolution of helium bubbles in He-irradiated Inconel 617: Experimental observation and anisotropic phase-field simulation 氦辐照Inconel 617中氦气泡的空间非均质演化：实验观察和各向异性相场模拟

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials

Pub Date : 2026-03-01 Epub Date: 2025-12-28 DOI: 10.1016/j.jnucmat.2025.156417

Chong Liu , Dazhao Cheng , Jiahui Qu , Dehui Li , Yan Zhao , Jing Zhang

The evolution of helium bubbles in nickel-based alloys poses significant challenges to the structural integrity of nuclear reactor components. This study investigates the spatial heterogeneity and anisotropic evolution of helium bubbles in Inconel 617 under He ion irradiation (1 MeV, 3 × 10¹⁶ ions/cm², 830 °C) using a coupled experimental and anisotropic phase-field approach. Transmission electron microscopy reveals distinct bubble characteristics: the (Ni,Cr)O oxide/matrix interface exhibits the highest bubble density, while both the interface and the oxide interior share similar, fine bubble sizes (∼2.4 nm). In contrast, the Ni matrix hosts larger bubbles (∼3.8 nm) at a lower density. The anisotropic phase-field model, developed to quantitatively interpret these observations, identifies the coherent oxide interface as a potent defect sink. Its strong absorption of helium and vacancies promotes dense bubble nucleation while inducing a local vacancy depletion that suppresses coarsening in the oxide. Conversely, in the matrix, long-range diffusion enables the growth of sparse, large bubbles. Critically, the simulation reproduces the experimentally observed quadrilateral bubble morphology in the matrix, confirming the dominance of surface energy anisotropy in shaping bubbles. This work provides the first quantitative interpretation of anisotropic bubble evolution at oxide interfaces in IN617, highlighting the critical interplay between defect sink strength and crystallographic anisotropy. The coupled methodology establishes a predictive framework for designing radiation-tolerant microstructures.

镍基合金中氦气泡的演化对核反应堆部件的结构完整性提出了重大挑战。采用实验和各向异性相场耦合方法研究了He离子辐照（1 MeV, 3 × 10¹26 ions/cm²，830°C）下Inconel 617中氦气泡的空间非均质性和各向异性演化。透射电镜显示出明显的气泡特征：（Ni,Cr）O氧化物/基体界面显示出最高的气泡密度，而界面和氧化物内部都具有相似的细气泡尺寸（~ 2.4 nm）。相比之下，Ni基体在较低密度下具有较大的气泡（~ 3.8 nm）。为定量解释这些观察结果而开发的各向异性相场模型将相干氧化物界面确定为有效的缺陷汇。它对氦和空位的强烈吸收促进了致密的气泡成核，同时诱导了局部空位耗尽，抑制了氧化物中的粗化。相反，在基体中，远距离扩散使稀疏的大气泡得以生长。重要的是，模拟再现了实验中观察到的四边形气泡在基体中的形态，证实了表面能各向异性在形成气泡中的主导作用。这项工作提供了IN617中氧化物界面各向异性气泡演化的第一个定量解释，突出了缺陷汇强度和晶体各向异性之间的关键相互作用。该耦合方法为设计耐辐射微结构建立了预测框架。

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引用次数: 0

Inducing δ-ferrite in 316NG austenitic stainless steel without welding: Microstructure and SCC resistance in simulated BWR environment 316NG奥氏体不锈钢不焊接诱导δ-铁素体：模拟BWR环境下的显微组织和抗SCC性能

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials

Pub Date : 2026-02-01 Epub Date: 2025-12-17 DOI: 10.1016/j.jnucmat.2025.156383

Zhao-Wei Fu, Hiroshi Abe, Yutaka Watanabe

This study aims to develop a stainless-steel microstructure with enhanced resistance to stress corrosion cracking propagation in high-temperature water by uniformly distributing island shaped δ-ferrite along grain boundaries. A partially melted zone near the fusion boundary was reproduced through weld-simulation heat treatments to investigate the formation behavior of δ-ferrite. The key material factors and optimal heat treatment conditions required to obtain a microstructure with uniformly and widely distributed island-shaped δ-ferrite along grain boundaries were examined. Crack growth tests were then conducted in a simulated boiling water reactor environment to evaluate the effect of δ-ferrite on crack propagation. The effect of the δ-ferrite on the crack growth rate was not clear. This was attributed to the low crack growth rate and the insufficient distribution of δ-ferrite along the crack propagation path. An investigation of all secondary cracks observed in the cross sections that encountered δ-ferrite revealed that, although the volume fraction of δ-ferrite along the total crack length was extremely small, >50% of the crack tips were located at δ-ferrite. This result suggests that δ-ferrite possesses resistance to crack propagation.

本研究旨在通过沿晶界均匀分布岛状δ铁素体，建立一种耐高温水中应力腐蚀裂纹扩展的不锈钢组织。通过模拟焊接热处理重现了熔合边界附近的部分熔化区，研究了δ-铁氧体的形成行为。研究了获得沿晶界均匀分布的岛状δ铁素体组织所需的关键材料因素和最佳热处理条件。在模拟沸水反应堆环境下进行了裂纹扩展试验，以评估δ-铁素体对裂纹扩展的影响。δ-铁素体对裂纹扩展速率的影响不明显。这主要是由于裂纹扩展速率低，δ-铁素体沿裂纹扩展路径分布不充分所致。对遇到δ铁素体的截面上观察到的所有次生裂纹的研究表明，尽管δ铁素体沿裂纹总长度的体积分数非常小，但50%的裂纹尖端位于δ铁素体。这表明δ-铁素体具有抗裂纹扩展的能力。

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引用次数: 0