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Дата издания
08.04.2025Область исследования
Тип исследования
Аннотация (краткое описание)
The binary intermetallic compound of beryllium and titanium (Be12Ti) is an advanced material for DEMO-type fusion reactors as a neutron multiplier in breeder blankets. Titanium beryllide has a high melting point (∼1873 K), high oxidation resistance and low swelling, which makes it attractive for use in fission and fusion reactors. The study of its behavior in a radiation field is of utmost importance from the point of view of practical application of titanium beryllide in nuclear installations. Based on this, at the Institute of Nuclear Physics (Kazakhstan), R&D is underway to characterization of industrial fabricated titanium beryllide (Be12Ti) at JSC “Ulba Metallurgical Plant” (Kazakhstan). Titanium beryllide samples were irradiated in the WWR-K reactor core to accumulate two integral neutron fluences of 1.6 × 1025 m-2 and 2.3 × 1025 m-2, in an inert environment and at low temperature to minimize gas migration from the samples. The present work presents the results of post reactor studies to determine the amount of generated tritium and helium in irradiated Be12Ti samples. The studies were carried out by thermodesorption spectrometry (TDS) method with mass-spectra control of gas composition. Mass spectra of gas extraction from titanium beryllide irradiated to different neutron fluences and heated up to 1173–1223 K at different heating rates (5, 10, 20 K/min) are presented. The kinetic parameters of tritium desorption from Be12Ti were determined, and the activation energy was estimated for each fluence achieved. © 2025 Elsevier B.V.DOI
10.1016/j.fusengdes.2025.115069Тип публикаций
Сведения о финансировании
Ministry of Education and Science of the Republic of Kazakhstan, BR24993119Данный документ располагается в коллекциях
Международные публикации ученых SU
Scopus
Файлы документа
1-s2.0-S0920379625002662-main.pdf