Journal of Nuclear Materials最新文献_第8页

Synergistic effect of Zr2Si diffusion barrier and Al2O3/Cr2O3 scale in PEO/CrAlSi coating for enhanced steam oxidation resistance of Zr-2 alloy cladding PEO/CrAlSi涂层中Zr2Si扩散阻挡层和Al2O3/Cr2O3垢对Zr-2合金包层抗蒸汽氧化性能的协同作用

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

Journal of Nuclear Materials

Pub Date : 2025-11-12 DOI: 10.1016/j.jnucmat.2025.156299

Qian Zhou , Xin Li , Lijiao Wang , Luqi Chai , Xiaoyue Jin , Chi Xu , Bin Liao , Luwei Xue , Rongshan Wang , Wanxiang Zhao , Wenbin Xue

To improve the high-temperature steam oxidation resistance of Zr alloys under loss-of-coolant accident (LOCA) conditions, a ZrO₂/CrAlSi composite coating was fabricated on Zr-2 alloy via plasma electrolytic oxidation (PEO) followed by filtered cathodic vacuum arc deposition (FCVAD). The coating exhibited superior protection in 1100 °C steam for up to 180 min, with oxidation kinetics transitioning from parabolic to accelerated behavior after 144 min. Microstructural analysis revealed that outward diffusion of Cr and Al formed a protective Al₂O₃/Cr₂O₃ scale, significantly reducing oxygen permeability compared to conventional Cr coatings (∼1 μm vs. 4.9–8 μm oxide thickness at 60 min). Inward Si migration generated a Zr₂Si diffusion barrier within the PEO interlayer, effectively suppressing Cr penetration into the substrate. However, prolonged exposure (180 min) led to Zr₂Si oxidation and the precipitation of brittle CrZr₂(Al,O) phases. The PEO interlayer played a critical role in mitigating elemental interdiffusion (Zr, Cr, Al, Si, O) and reducing oxygen permeability, thereby enhancing coating durability. This study demonstrates that the synergistic effects of Al₂O₃/Cr₂O₃ scale formation, Zr₂Si diffusion barrier, and PEO-mediated diffusion control significantly enhance the oxidation resistance of Zr alloys, making the PEO/CrAlSi coating a promising candidate for accident-tolerant fuel cladding applications.

为了提高Zr合金在失冷剂（LOCA）条件下的高温蒸汽氧化性能，采用等离子体电解氧化(PEO) +过滤阴极真空电弧沉积（FCVAD）法制备了Zr-2合金表面的ZrO2/CrAlSi复合涂层。涂层在1100°C蒸汽中保温180分钟，氧化动力学在144分钟后从抛物线态转变为加速态。显微结构分析表明，Cr和Al向外扩散形成了Al2O3/Cr2O3保护层，与传统Cr涂层相比，显著降低了氧渗透性（60分钟时，氧化厚度为4.9-8 μm）。Si向内迁移在PEO中间层内形成了Zr2Si扩散屏障，有效抑制了Cr向基体的渗透。然而，长时间暴露（180 min）导致Zr2Si氧化，析出脆性的CrZr2（Al，O）相。PEO中间层在减缓元素间相互扩散（Zr、Cr、Al、Si、O）和降低氧渗透性方面发挥了关键作用，从而提高了涂层的耐久性。该研究表明，Al2O3/Cr2O3结垢、Zr2Si扩散屏障和PEO-扩散控制的协同效应显著提高了Zr合金的抗氧化性，使PEO/CrAlSi涂层成为耐事故燃料包壳应用的有希望的候选材料。

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引用次数: 0

Micro-tensile testing of neutron-irradiated Al/Zr and Zr/U-Mo diffusion bonds 中子辐照Al/Zr和Zr/U-Mo扩散键的微拉伸试验

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

Journal of Nuclear Materials

Pub Date : 2025-11-11 DOI: 10.1016/j.jnucmat.2025.156296

Jason L. Schulthess, Cameron B. Howard, Tanner J. Mauseth, Christopher Bearcroft

This study focuses on micro-tensile testing of neutron-irradiated Al/Zr and Zr/U-Mo diffusion bonds, which are integral to the structure and performance of nuclear fuel plates used in the fuel being developed for U.S. high-power research reactors. During fabrication, two distinct diffusion bonds occur—one at the Zr/U-10Mo interface via roll bonding, and the Zr/Al interface via hot isostatic pressing at 833 K.

This work utilizes micro-tensile testing specimens approximately 7 × 7 × 18 μm³, which are sufficiently large to encompass the identified diffusion zones to evaluate the failure strength and identify the failure location. For the Zr/Al interface, all failures occurred in the bulk aluminum. The average yield strength, ultimate strength, and strain at failure for the two parent samples were: 125 ± 10 MPa, 139 ± 24 MPa, 156 ± 21 MPa, 185 ± 14 MPa, 37.9 ± 5.6 %, and 29.7 ± 3.4 %, respectively. For specimens across the Zr/U-Mo interface, failures occurred either in the bulk Zr or U-Mo, with no failures observed in the diffusion region. For specimens that failed in the bulk Zr the failure strength and strain for the two parent samples were 570 MPa, 710 ± 131 MPa, and 43.3 %, 27.3 ± 6.6 % respectively. The specimens that failed in the bulk U-Mo had failure strengths and strains of 596 ± 32 MPa, 548 ± 124 MPa, and 2.2 ± 1.3 %, 1.5 ± 0.6 % respectively.

These findings support the development of accurate thermo-mechanical models for irradiated fuel performance by identifying the mechanical limits and failure locations within the bonded regions.

这项研究的重点是中子辐照Al/Zr和Zr/U-Mo扩散键的微拉伸测试，这是美国大功率研究堆正在开发的燃料中使用的核燃料板结构和性能的组成部分。在制备过程中，两种不同的扩散键发生——一种在Zr/U-10Mo界面上通过滚焊，另一种在833 K下通过热等静压形成Zr/Al界面。本工作采用约7 × 7 × 18 μm3的微拉伸试样，试样足够大，可以覆盖已确定的扩散区，以评估破坏强度并确定破坏位置。对于Zr/Al界面，所有失效都发生在大块铝中。两种母材的平均屈服强度、极限强度和破坏应变分别为：125±10 MPa、139±24 MPa、156±21 MPa、185±14 MPa，分别为37.9±5.6%和29.7±3.4%。对于穿过Zr/U-Mo界面的试样，破坏发生在大块Zr或U-Mo中，而在扩散区未观察到破坏。试样破坏时，两种母材试样的破坏强度和应变分别为570 MPa、710±131 MPa和43.3%、27.3±6.6%。U-Mo块体破坏试样的破坏强度和应变分别为596±32 MPa、548±124 MPa和2.2±1.3%、1.5±0.6%。这些发现通过确定粘合区域内的机械极限和失效位置，为辐照燃料性能的精确热力学模型的发展提供了支持。

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引用次数: 0

Molecular dynamics simulation of pre-strain on 3C-SiC irradiation damage behavior 预应变对3C-SiC辐照损伤行为的分子动力学模拟

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

Journal of Nuclear Materials

Pub Date : 2025-11-11 DOI: 10.1016/j.jnucmat.2025.156298

Bingfei Liu , Chenyu Pan , Wenping Wu

3C-SiC exhibited excellent mechanical and radiation-resistant properties, making it suitable for nuclear and aerospace applications. During service, pre-strain from operational environments could significantly influence its irradiation damage behavior. This study employed molecular dynamics simulations to investigate the effects of tensile and shear pre-strain on the irradiation response of 3C-SiC. Results indicated that tensile pre-strain markedly increased both the peak and stable number of defects, with a more pronounced effect on Carbon vacancies, vacancies cluster size. Shear pre-strain could induce significant variations in both the defect evolution and distribution in specific conditions even made defects approximate a linear distribution, despite an identical PKA incident direction. This phenomenon depended on PKA energy and temperature. Defect formation energy calculations revealed a reduction under tensile strain, while it remains largely unchanged under shear and the results of displacement threshold energy decreased under tensile pre-strain, while variations were observed under shear pre-strain. These findings elucidated the influence mechanisms of pre-strain on the irradiation damage process, particularly the unique mechanism associated with shear pre-strain.

3C-SiC具有优异的机械和抗辐射性能，适用于核和航空航天应用。在服役过程中，作业环境的预应变对其辐照损伤行为有显著影响。本研究采用分子动力学模拟研究了拉伸和剪切预应变对3C-SiC辐照响应的影响。结果表明，拉伸预应变显著增加了峰值缺陷数和稳定缺陷数，对碳空位、空位簇尺寸的影响更为显著。剪切预应变在特定条件下会引起缺陷演化和分布的显著变化，甚至使缺陷近似线性分布，尽管PKA入射方向相同。这种现象与PKA能量和温度有关。缺陷形成能计算结果显示，拉伸应变作用下缺陷形成能减小，剪切作用下缺陷形成能基本保持不变；位移阈值能计算结果显示，拉伸预应变作用下缺陷形成能减小，而剪切预应变作用下缺陷形成能发生变化。这些发现阐明了预应变对辐照损伤过程的影响机制，特别是与剪切预应变相关的独特机制。

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引用次数: 0

A comparative study on the corrosion resistance and microstructure stability of Fe-Ni-Cr-Al-Si based austenitic steel in lead-bismuth eutectic with 10-6 wt.% oxygen at 600 and 650°C for up to 6000 h Fe-Ni-Cr-Al-Si基奥氏体钢在10- 6wt .%氧、600℃和650℃共晶6000 h下的耐蚀性和组织稳定性对比研究

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

Journal of Nuclear Materials

Pub Date : 2025-11-10 DOI: 10.1016/j.jnucmat.2025.156295

Decang Zhang , Xiaoxin Zhang , Sicheng Wang , Feifei Zhang , Hao Ren , Jun Zhang , Qingzhi Yan

Six austenitic stainless steels with compositions in the range of Fe–(15∼17)Ni–(12∼14)Cr–(0∼3)Al–(0∼3)Si–1Nb–0.1Y–0.2C were developed and their corrosion resistance and microstructure stability were systematically evaluated in liquid lead-bismuth eutectic containing 10^-6 wt.% oxygen at 600°C and 650°C for up to 6000 h. The results revealed that at 600°C, the steels 17Ni14Cr3Al1Si, 17Ni14Cr3Si, and 15Ni14Cr3Al1Si demonstrated excellent long-term corrosion resistance and retained stable microstructures. However, at 650°C, only 15Ni14Cr3Al1Si maintained both corrosion resistance and microstructure stability, indicating its suitability for high-temperature lead-bismuth eutectic environments.

制备了6种成分在Fe - (15 ~ 17)Ni - (12 ~ 14)Cr - (0 ~ 3)Al - (0 ~ 3) Si-1Nb-0.1Y-0.2C范围内的奥氏体不锈钢，并在含10-6 wt.%氧的铅铋共晶液中，在600℃和650℃下，系统地评价了它们的耐蚀性和显微组织稳定性。结果表明，在600℃下，17Ni14Cr3Al1Si、17Ni14Cr3Si、和15Ni14Cr3Al1Si表现出优异的长期耐蚀性和保持稳定的显微组织。然而，在650°C时，只有15Ni14Cr3Al1Si同时保持耐蚀性和组织稳定性，表明其适合高温铅铋共晶环境。

引用次数: 0

Effect of Si content on dislocation loop evolution and hardening behavior of irradiated Al-Mg-Si alloys Si含量对辐照Al-Mg-Si合金位错环演变及硬化行为的影响

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

Journal of Nuclear Materials

Pub Date : 2025-11-09 DOI: 10.1016/j.jnucmat.2025.156294

Shikun Zhu , Ming Cao , Ziqi Cao , Ling Li , Zuojiang Wang , Yizhong Yang , Hongchang Wang , Xujia Wang , Guang Ran

Neutron irradiation will induce irradiation damage and transmute Al to Si in Al alloys, obviously altering their microstructure and severely deteriorating mechanical properties. However, how transmuted silicon affects the evolution of dislocation loops and hardening behavior of Al alloys is still not fully understood. In this study, Al-2.64Mg alloy with different Si contents (0.02∼2.98 wt.%) were designed to study the above scientific questions using in-situ ion irradiation in TEM, nanoindentation, and positron annihilation Doppler broadening spectroscopy. The results show that the solute clusters were formed under low-dose irradiation with higher Si content promoting cluster formation. These clusters together with precipitates promoted the nucleation of dense and small dislocation loops, especially near second-phase regions. Although loop density increased with Si content, nanoindentation revealed that irradiation hardening decreased. This counterintuitive trend is attributed to two factors: (1) dislocation loops near precipitates grow more slowly than those in the matrix, limiting hardening; (2) amorphous Si-rich particles reduce the local barrier strength of precipitate-adjacent loops, lowering the irradiation-induced loop contribution. Moreover, precipitation strengthening remains positive and is dominated by amorphous Si-rich precipitates. These findings will deepen our understanding of how the content of Si atoms derived from transmutation affects irradiation damage in aluminum alloy.

中子辐照会引起辐照损伤，使铝合金中的Al转变为Si，使其显微组织发生明显改变，力学性能严重恶化。然而，相变硅如何影响位错环的演化和铝合金的硬化行为仍不完全清楚。本研究设计了不同Si含量（0.02 ~ 2.98 wt.%）的Al-2.64Mg合金，利用原位离子辐照、纳米压痕和正电子湮没多普勒展宽光谱对上述科学问题进行了研究。结果表明，高Si含量的低剂量辐射促进了溶质团簇的形成。这些团簇与析出相一起促进了密集和小的位错环的形核，特别是在第二相区域附近。虽然环密度随Si含量的增加而增加，但纳米压痕显示辐照硬化降低。这种反直觉的趋势归因于两个因素：(1)析出相附近的位错环比基体中的位错环生长得慢，限制了硬化；(2)非晶态富硅粒子降低了邻近沉淀环的局部势垒强度，降低了辐射诱导环的贡献。此外，析出强化仍为正强化，且以非晶富硅相为主。这些发现将加深我们对嬗变产生的Si原子含量如何影响铝合金辐照损伤的理解。

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引用次数: 0

Effect of dissolved hydrogen on crack propagation of cold-worked 316LN SS under periodic loading in simulated PWR primary water 模拟压水堆原生水循环加载下溶解氢对316LN不锈钢冷加工裂纹扩展的影响

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

Journal of Nuclear Materials

Pub Date : 2025-11-08 DOI: 10.1016/j.jnucmat.2025.156288

Panpan Wu , Xiujie Wang , Entong Li , Qianwu Li , Chengtao Li , Zhanpeng Lu , Junjie Chen , Tongming Cui , Xinhe Xu , Tetsuo Shoji

Corrosion fatigue propagation behaviors of the 20 % cold work 316LN (20CW316LN) stainless steel (SS) were investigated in a simulated primary water reactor (PWR) coolant with various dissolved hydrogen (DH) of 0 to 50 cm³ (STP) H₂/kg H₂O (cc/kg) at 320 °C under cyclic asymmetric load mode with load rising time of 2000 s and load decline time of 200 s. The corrosion fatigue crack propagation rate (CPR) of 20CW316LN within the ΔK range of about 10 to 13 MPa m^0.5 was lower than that of AR316LN under similar conditions. A lowest corrosion fatigue CPR was found at DH=30 cc/kg for both AR316LN and 20CW316LN. A highest mitigating effect of cold work on corrosion fatigue CPR was also observed at DH=30 cc/kg. The V-shaped dependence of corrosion fatigue CPR on DH was interpreted under the framework of the crack propagation kinetics under the combined processes of active dissolution and film forming during the load rising period. Prior-cold work decreased the crack opening displacement rate and the resultant crack tip strain rate, which contributed to the decrease in the crack propagation rate during the loading rising period and the resultant crack propagation rate.

研究了20%冷加工316LN （20CW316LN）不锈钢（SS）在模拟一次水堆（PWR）冷却剂中，在320℃条件下，不同溶解氢（DH）为0 ~ 50 cm3 (STP) H2/kg H2O (cc/kg)，载荷上升时间为2000 s，载荷下降时间为200 s的循环非对称加载模式下的腐蚀疲劳扩展行为。在ΔK约10 ~ 13 MPa m0.5范围内，20CW316LN的腐蚀疲劳裂纹扩展速率（CPR）低于AR316LN。当DH=30 cc/kg时，AR316LN和20CW316LN的腐蚀疲劳CPR最低。当DH=30 cc/kg时，冷加工对腐蚀疲劳CPR的缓解效果最高。在载荷上升期活性溶解和成膜联合作用下的裂纹扩展动力学框架下，解释了腐蚀疲劳CPR对DH的v型依赖关系。预冷加工降低了裂纹张开位移速率和裂纹尖端应变速率，从而降低了加载上升期裂纹扩展速率和裂纹扩展速率。

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引用次数: 0

Significant amplification of irradiation dose effects by hydrogen-helium and the mechanism based on rate theory 氢氦辐照剂量效应的显著放大及基于速率理论的机理

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

Journal of Nuclear Materials

Pub Date : 2025-11-07 DOI: 10.1016/j.jnucmat.2025.156292

Rui Yan , Zepeng Yin , Liping Guo , Yiheng Chen , Junjie Cao , Yunxiang Long , Ziyang Xie , Hongtai Luo , Wenbin Lin

The disparity in dose rates between ion irradiation and neutron irradiation results in distinct microscopic defect structures in irradiated materials. Moreover, the hydrogen-helium synergistic effect further complicates the evolution of the defects. Therefore, these two effects are the two most of concerning issues in simulating neutron irradiation using ion irradiation. In order investigate the synergistic effect between dose rate and hydrogen-helium gas atom on the evolution of dislocation loops and material hardening, both single- and multi-beam irradiation schemes with a dose rate difference of 10 times were implemented on China Low-Activation Martensitic (CLAM) steel. It was found that as the dose rate increased, the average size of the dislocation loops became smaller while the number density elevated, and the irradiation-induced hardening was more pronounced, under both single- and multi- beam irradiations. Interestingly, it was found that the presence of hydrogen and helium significantly amplified the difference in dislocation loops and hardening caused by different dose rates. A mechanism based on rate theory and dislocation loop growth equations was proposed to elaborate this dose rate effect. Moreover, a clear physical picture of how dose rate, sink strength, and hydrogen-helium gas atoms collectively affect the evolution of dislocation loops has been raised. The present study provides a valuable reference for the evaluation of candidate structural materials of future fusion reactors using ion irradiation.

离子辐照和中子辐照的剂量率差异导致辐照材料的微观缺陷结构不同。此外，氢氦协同效应进一步复杂化了缺陷的演变。因此，这两种效应是离子辐照模拟中子辐照时最值得关注的两个问题。为了研究剂量率和氢氦原子对位错环演化和材料硬化的协同作用，对中国低活化马氏体（CLAM）钢进行了剂量率差10倍的单束和多束辐照。结果表明，在单束和多束辐照下，随着剂量率的增加，位错环的平均尺寸变小，而数量密度增大，辐照诱导硬化更加明显。有趣的是，发现氢和氦的存在显著放大了不同剂量率引起的位错环和硬化的差异。提出了基于速率理论和位错环生长方程的剂量率效应机理。此外，还提出了剂量率、沉降强度和氢氦原子共同影响位错环演化的清晰物理图景。本研究为今后利用离子辐照评价核聚变反应堆候选结构材料提供了有价值的参考。

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引用次数: 0

Phase investigation in the eutectic solidification of the U–Fe–O system in air by TG–DTA, PXRD and SEM–EDX 用TG-DTA、PXRD和SEM-EDX研究空气中U-Fe-O体系共晶凝固的物相

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

Journal of Nuclear Materials

Pub Date : 2025-11-07 DOI: 10.1016/j.jnucmat.2025.156287

Toshiki Iwahara , Daisuke Akiyama , Yuki Yokota , Akira Kirishima

The U–Fe–O ternary system is important for understanding the fuel debris. However, the phase transition temperature of the system and the formation sequence of U–Fe complex oxides during cooling have not been well investigated. In this study, we determined the reaction temperature of this system using thermogravimetry–differential thermal analysis. Mixed powder samples of U₃O₈ and Fe₂O₃ were heated and quenched at a high temperature, and the formed phase was analyzed by powder X-ray diffractometry and scanning electron microscopy–energy dispersive X-ray spectroscopy. FeUO₄ was formed during the cooling of the Fe-rich sample. Furthermore, the eutectic solidification temperature of the Fe-rich composition was approximately 20 K lower than the eutectic melting temperature at a heating rate of 10 K/min.

U-Fe-O三元体系对理解燃料碎片具有重要意义。然而，系统的相变温度和冷却过程中U-Fe络合物氧化物的形成顺序尚未得到很好的研究。在这项研究中，我们用热重-差热分析法确定了该体系的反应温度。对U3O8和Fe2O3混合粉末样品进行高温加热淬火，采用粉末x射线衍射仪和扫描电镜-能量色散x射线能谱分析形成的相。富铁样品在冷却过程中形成FeUO4。当升温速率为10 K/min时，富铁组分的共晶凝固温度比共晶熔化温度低约20 K。

引用次数: 0

Effect of magnesium ions and sulfate on the corrosion of Q235B low carbon steel in simulated flowing groundwater 镁离子和硫酸盐对Q235B低碳钢在模拟流动地下水中腐蚀的影响

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

Journal of Nuclear Materials

Pub Date : 2025-11-07 DOI: 10.1016/j.jnucmat.2025.156291

Jianzhen Qiu , Tao Yu , Minhao Mu , Mingrui Feng , Qiburi Bao , Zhen Dong , Miao Yang

The effect of different flow rates and groundwater ions (SO₄²⁻, Mg²⁺) in simulated flowing groundwater (SG) solutions on the corrosion behavior of Q235B low carbon steel, a potential material for packaging containers for high level wastes, was systematically investigated in the paper. The results of electrochemical measurements, weight loss experiments, and characterization of the steel in different simulated flow solutions showed that the corrosion product of Q235B low-carbon steel in static SG solution is thinner and denser, with a corrosion rate of 46.5 μm/y; The increase in flow rate leads to a gradual rise in corrosion current density and corrosion rate, but the growth trend gradually slows down. At the same time, it causes the outer layer structure of the generated corrosion product to be loose and have poor adhesion. At 900 rpm, the corrosion rates in SG + Na₂SO₄ and SG + MgSO₄ solutions increase to 321.3 μm/y and 367.1 μm/y, respectively. The addition of SO₄²⁻ does not change the composition of the corrosion product (mainly FeOOH, Fe₃O₄ and Fe₂O₃), but leads to a lower solution resistance. The addition of Mg²⁺ causes differences in the corrosion product. On the one hand, it promotes the formation of carbonate precipitation; on the other hand, it undergoes ion exchange with Fe²⁺ to form magnesium-containing iron oxides (such as Mg Fe₂O₄), which destroys the compactness of the corrosion product film. The addition of both SO₄²⁻ and Mg²⁺ accelerates the corrosion process.

本文系统研究了模拟流动地下水（SG）溶液中不同流速和地下水离子（SO42−、Mg2+）对高放废物包装容器材料Q235B低碳钢腐蚀行为的影响。电化学测试、失重实验和不同模拟流动溶液中碳钢的表征结果表明：Q235B低碳钢在静态SG溶液中的腐蚀产物更薄、更致密，腐蚀速率为46.5 μm/y；随着流量的增加，腐蚀电流密度和腐蚀速率逐渐上升，但增长趋势逐渐减缓。同时，造成生成的腐蚀产物外层结构疏松，附着力差。在900 rpm时，SG + Na2SO4和SG + MgSO4溶液中的腐蚀速率分别增加到321.3 μm/y和367.1 μm/y。SO42−的加入不会改变腐蚀产物的组成（主要是FeOOH、Fe3O4和Fe2O3），但会降低腐蚀产物的耐溶性。Mg2+的加入导致了腐蚀产物的不同。一方面促进了碳酸盐沉淀的形成；另一方面，它与Fe2⁺发生离子交换，形成含镁氧化铁（如Mg Fe2O4），破坏了腐蚀产物膜的致密性。SO42−和Mg2+的加入加速了腐蚀过程。

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引用次数: 0

Influence of intermediate heat treatment on the creep properties of CZ1 zirconium alloys: Creep mechanisms and mechanistic modeling 中间热处理对CZ1锆合金蠕变性能的影响：蠕变机理和力学模型

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

Journal of Nuclear Materials

Pub Date : 2025-11-07 DOI: 10.1016/j.jnucmat.2025.156289

Weitong Lin, Weicai Li, Qingyang Lv, Liutao Chen, Libin Zhang, Jing Hu

Intermediate heat treatment is one of the essential processes during the manufacturing of zirconium (Zr) alloy cladding for nuclear applications. However, the influence of intermediate heat treatment on the creep properties of Zr alloys remains unclear. Here, we uncover the effect of intermediate annealing temperature on the microstructure and creep mechanisms of CZ1 Zr alloys via combining comprehensive electron microscopy characterizations and mechanistic modeling. It is found that increasing intermediate annealing temperature gives rise to a larger size of grains and second-phase particles, but a lower density of dislocations and second-phase particles. Internal pressure creep tests at 673 K demonstrated that a higher intermediate annealing temperature results in a slower creep rate at the hoop stress of 130 MPa but a faster creep rate at the hoop stress of 200 MPa. By performing microstructure-based mechanistic creep modeling, it is revealed that increasing intermediate annealing temperature can enhance the dislocation creep rate while reducing the Coble creep rate, and the contribution of dislocation and Coble creep mechanisms at different stress levels determines the creep behavior of Zr alloys. Our results provide new insights into the relationship between manufacturing processes and creep mechanisms of Zr alloys for developing the optimum creep properties.

中间热处理是制造核用锆合金包层的重要工艺之一。然而，中间热处理对Zr合金蠕变性能的影响尚不清楚。本文通过综合电镜表征和力学建模相结合的方法，揭示了中间退火温度对CZ1 Zr合金显微组织和蠕变机理的影响。随着中间退火温度的升高，晶粒尺寸和第二相颗粒尺寸增大，但位错密度和第二相颗粒密度减小。673 K的内压蠕变试验表明，较高的中间退火温度在130 MPa环向应力下蠕变速率较慢，而在200 MPa环向应力下蠕变速率较快。通过建立基于微观组织的蠕变模型，发现提高中间退火温度可以提高位错蠕变速率，降低Coble蠕变速率，不同应力水平下位错和Coble蠕变机制的贡献决定了Zr合金的蠕变行为。我们的研究结果为研究Zr合金的蠕变机理与制造工艺之间的关系提供了新的见解，为开发最佳的蠕变性能提供了新的思路。

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引用次数: 0