辨别各种辐照模式对 Zircaloy-4 腐蚀的影响

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2024-11-08 DOI:10.1016/j.jnucmat.2024.155505

Peng Wang , Bruce Kammenzind , Richard Smith , Arthur Motta , Matthieu Aumand , Damien Kaczorowski , Mukesh Bachhav , Gary Was

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引用次数: 0

摘要

本研究利用质子辐照，研究了在模拟压水堆（PWR）的氢化水环境中，若干因素对锆合金-4 腐蚀动力学的单独影响。通过同时进行辐照-腐蚀和高压釜腐蚀，我们分别研究了(i) 预辐照对改变材料结构的影响，(ii) 辐照对腐蚀过程中氧化层生长过程中产生缺陷的影响，以及 (iii) 辐照对腐蚀过程中通过辐射分解提高腐蚀电位的影响。为了复制中子辐照的微观结构，采用了两种质子预辐照方案：附表 1（在 350 °C 等温辐照至 5 分帕）用于模拟高温压水堆条件，附表 2（两步过程：在 -10 °C 下辐照至 2.5 分帕，然后在 350 °C 下辐照至 2.5 分帕）用于模拟低温压水堆和沸水堆条件。在 320 ℃ 下进行 360 天的长期高压釜腐蚀测试表明，未经过辐照的样品与按照任一计划进行预辐照的样品之间没有明显差异，所有样品在过渡前状态下都表现出亚立方动力学。预辐照样品进行了同时辐照腐蚀（SIC）试验，在 320 °C 水中进行腐蚀，同时进行质子辐照。与高压灭菌条件相比，所有经过 SIC 试验的样品的腐蚀速度都有所加快，在样品的非预辐照区域观察到的腐蚀速度增幅最大。与 SIC 条件下的非预辐照区域相比，两种辐照方案的预辐照都会导致腐蚀速度减慢。在 SIC 试验中观察到的辐射分解程度超过了典型的压水堆条件，接近于在生物武器反应堆中发现的水平。放射性溶解产物被确定为加速腐蚀的主要因素，放射性溶解棒试验也证实了这一点。这些发现强调了辐照、腐蚀和水化学在决定核反应堆环境中 Zircaloy-4 腐蚀动力学方面错综复杂的相互作用。

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Discerning the effect of various irradiation modes on the corrosion of Zircaloy-4

Using proton irradiation, this study investigates the individual influence of several factors on the corrosion kinetics of Zircaloy-4 in a hydrogenated water environment simulating a Pressurized Water Reactor (PWR). Using both simultaneous irradiation-corrosion and autoclave corrosion, we separately examine (i) the effect of pre-irradiation on modifying the structure of the material, (ii) the impact of irradiation on creating defects in the growing oxide layer during corrosion, and (iii) the influence of irradiation on increasing the corrosion potential through radiolysis during corrosion. To replicate the neutron-irradiated microstructure, two proton pre-irradiation schedules were employed: Schedule 1 (isothermal irradiation at 350 °C to 5 dpa) to simulate high-temperature PWR conditions, and Schedule 2 (two-step process: irradiation to 2.5 dpa at -10 °C followed by 2.5 dpa at 350 °C) to simulate lower temperature PWR and Boiling Water Reactor (BWR) conditions. Long-term autoclave corrosion testing for 360 days at 320 °C revealed no significant difference between unirradiated samples and those pre-irradiated according to either schedule, with all samples exhibiting sub-cubic kinetics within the pre-transition regime. Pre-irradiated samples underwent Simultaneous Irradiation Corrosion (SIC) tests, corroding in 320 °C water while being irradiated with protons. Corrosion was found to accelerate in all SIC-tested samples relative to autoclave conditions, with the greatest increase observed in non-pre-irradiated regions of the samples. Pre-irradiation with either schedule resulted in a slower corrosion rate compared to non-pre-irradiated regions under SIC conditions. The degree of radiolysis observed in the SIC tests surpassed typical PWR conditions, approaching levels found in BWRs. Radiolysis products were identified as a primary contributors to accelerated corrosion, corroborated by radiolysis bar tests. These findings underscore the intricate interactions between irradiation, corrosion, and water chemistry in determining Zircaloy-4 corrosion kinetics within nuclear reactor environments.

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.