Effect of neutron irradiation on high-temperature corrosion of titanium beryllide Be12Ti in a steam-argon environment
Shaimerdenov A. Askerbekov S. Chikhray Y. Silnyagin P. Bugybay Z. Akhanov A. Kulsartov T. Kenzhina I. Zaurbekova Z. Larionov A. Zholdybayev T.
January 2026Elsevier B.V.
Journal of Nuclear Materials
2026#618
In this paper, we investigate the high-temperature corrosion of industrial titanium beryllide Be12 Ti following reactor irradiation at a power of 6 MW. The irradiation was conducted at an approximate temperature of 325 K and an integral neutron flux density of 1.1 × 1014 n/cm2/s. The irradiation duration lasted for 168 and 252 effective days, resulting in integral neutron fluences of 1.6 × 1021 n/cm2 for a batch of samples of the first level (F-I) and 2.3 × 1021 n/cm2 for a batch of samples of the second level (F-II). Microstructural analysis of the samples revealed that neutron irradiation induces changes in grain texture, alters the porosity of the structure, and results in the accumulation of radiation defects. These radiation-induced changes in the properties of Be12Ti directly influence the corrosion processes. Post-radiation corrosion experiments were performed in a steam-argon environment at varying heating rates, and the released reaction products were analyzed using mass spectrometry. The primary focus was on a comparative analysis of the material activation parameters, as well as the effect of surface microstructure evolution on reactivity. The primary indicator of H2O interaction with the surface was the release of atomic hydrogen, which enabled us to quantify the interaction rate parameters. In F-I samples, the intensity of hydrogen release is lower, and the release peaks are shifted to higher temperatures, attributed to an enhanced grain texture and a greater accumulation of defects. In contrast, F-II samples exhibit more active hydrogen release at lower temperatures, which is due to rapid grain transformation and a predominance of open porosity. Thus, F-II samples are characterized by higher activation energy (Ea=66 kJ/mol) and pre- exponential factor (K0=1.9 s−1), while F-I samples show lower values (Ea=50 kJ/mol, K0=0.47 s−1). Copyright
Beryllide , Beryllium oxidation , High temperature corrosion , Hot isostatic pressing (HIP) , Neutron irradiation , Titanium beryllide (TiBe12)
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Institute of Nuclear Physics, Almaty, Kazakhstan
Institute of Experimental and Theoretical Physics, al-Farabi Kazakh National University, Almaty, Kazakhstan
Institute of Nuclear Physics
Institute of Experimental and Theoretical Physics
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Книга Публикация научной статьи Волощук 2026 Book Publication of a scientific article 2026