Lifetime of the stainless steel inner case of the waste disposal package under gamma irradiation

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

Journal of Nuclear Materials Pub Date : 2025-09-02 DOI:10.1016/j.jnucmat.2025.156146

Jan Stoulil , David Dobrev , Richard Bureš , Jaroslav Fojt , Vlastimil Miler

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Abstract

In this work, the kinetics of the dissolution of the passive layer of 316 L stainless steel was investigated in the environment of bentonite Černý Vrch (BCV). The composition of the passive layer was characterized using Mott-Schottky curves and XPS. The dissolution kinetics was studied using potentiostatic polarization in the bentonite pore solution and bentonite slurry, as well as exposures in the bentonite pore solution followed by analysis of the released ions using ICP-OES. For the dissolution of Cr from the passive layer, the presence of oxidizing radiolysis products is a key factor, while for the dissolution of Fe, the excitation of the charge carriers over a band gap by radiation is a more significant factor. Exposures in a bentonite pore solution allowed us to determine the kinetics of spontaneous dissolution of the passive layer, which in the repository geometry reaches an equilibrium state within 10³ years. Potentiostatic measurements allowed the steady state dissolution of the passive layer to be rapidly reached, which is at 2.23 × 10^–2 nm.a^-1. Based on the data obtained, numerical simulations were carried out and subsequently extrapolated the lifetime of the inner case of the container, which significantly exceeds the required 10⁶ years.

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废物处理包不锈钢内壳在γ射线照射下的寿命

本文研究了316l不锈钢钝化层在膨润土Černý Vrch （BCV）环境下的溶解动力学。采用Mott-Schottky曲线和XPS对钝化层的组成进行了表征。采用恒电位极化法研究了膨润土孔溶液和膨润土浆料的溶解动力学，并利用ICP-OES分析了膨润土孔溶液中释放的离子。对于Cr从钝化层中溶解，氧化辐射解产物的存在是一个关键因素，而对于Fe的溶解，辐射在带隙中激发载流子是一个更重要的因素。暴露在膨润土孔隙溶液中使我们能够确定被动层的自发溶解动力学，在储存库几何结构中，被动层在103年内达到平衡状态。恒电位测量可使钝化层的溶解迅速达到2.23 × 10-2 nm.a-1的稳态。根据获得的数据，进行了数值模拟，并随后推断出容器内壳的使用寿命，大大超过了要求的106年。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.