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Keywords = beryllides

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23 pages, 10093 KB  
Article
Phase Evolution and Synthesis of Be12 Nb Intermetallic Compound in the 800–1300 °C Temperature Range
by Sergey Udartsev, Inesh E. Kenzhina, Timur Kulsartov, Kuanysh Samarkhanov, Zhanna Zaurbekova, Yuriy Ponkratov, Alexandr Yelishenkov, Meiram Begentayev, Saulet Askerbekov, Aktolkyn Tolenova, Manarbek Kylyshkanov, Mikhail Podoinikov, Ainur Kaynazarova and Oleg Obgolts
Materials 2025, 18(12), 2915; https://doi.org/10.3390/ma18122915 - 19 Jun 2025
Viewed by 798
Abstract
Beryllium-based intermetallic compounds, such as Be12Nb, are attracting growing interest for their high thermal stability and potential to replace pure beryllium as neutron reflectors and multipliers in both fission and future fusion reactors, with additional applications in metallurgy, aerospace, and hydrogen [...] Read more.
Beryllium-based intermetallic compounds, such as Be12Nb, are attracting growing interest for their high thermal stability and potential to replace pure beryllium as neutron reflectors and multipliers in both fission and future fusion reactors, with additional applications in metallurgy, aerospace, and hydrogen technology. The paper presents the results of an investigation of the thermal treatment and phase formation of the intermetallic compound Be12Nb from a mixture of niobium and beryllium powders in the temperature range of 800–1300 °C. The phase evolution was assessed as a function of sintering temperature and time. A nearly single-phase Be12Nb composition was achieved at 1100 °C, while decomposition into lower-order beryllides such as Be17Nb2 occurred at temperatures ≥1200 °C, indicating thermal instability of Be12Nb under vacuum. Careful handling of sintering in low vacuum minimized oxidation, though signs of possible BeO formation were noted. The findings complement and extend earlier reports on Be12Nb synthesis via plasma sintering, mechanical alloying, and other powder metallurgy routes, providing broader insight into phase formation and synthesis. These results provide a foundation for optimizing the manufacturing parameters required to produce homogeneous Be12Nb-based components and billets at an industrial scale. Additionally, they help define the operational temperature limits necessary to preserve the material’s phase integrity during application. Full article
(This article belongs to the Section Advanced Materials Characterization)
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12 pages, 4889 KB  
Article
Blistering Behavior of Beryllium and Beryllium Alloy under High-Dose Helium Ion Irradiation
by Ping-Ping Liu, Qi-Cong Wang, Yu-Mei Jia, Wen-Tuo Han, Xiao-Ou Yi, Qian Zhan and Fa-Rong Wan
Materials 2024, 17(16), 3997; https://doi.org/10.3390/ma17163997 - 11 Aug 2024
Cited by 5 | Viewed by 1654
Abstract
Beryllium (Be) has been selected as the solid neutron multiplier material for a tritium breeding blanket module in ITER, which is also the primary option of the Chinese TBM program. But the irradiation swelling of beryllium is severe under high temperature, high irradiation [...] Read more.
Beryllium (Be) has been selected as the solid neutron multiplier material for a tritium breeding blanket module in ITER, which is also the primary option of the Chinese TBM program. But the irradiation swelling of beryllium is severe under high temperature, high irradiation damage and high doses of transmutation-induced helium. Advanced neutron multipliers with high stability at high temperature are desired for the demonstration power plant (DEMO) reactors and the China Fusion Engineering Test Reactor (CFETR). Beryllium alloys mainly composed of Be12M (M is W or Ti) phase were fabricated by HIP, which has a high melting point and high beryllium content. Beryllium and beryllide (Be12Ti and Be12W) samples were irradiated by helium ion with 30 keV and 1 × 1018 cm−2 at RT. The microstructures of Be, Be12Ti and Be12W samples were analyzed by SEM and TEM before and after ion irradiation. The average size of the first blistering on the surface of Be-W alloy is about 0.8 μm, and that of secondary blistering is about 79 nm. The surface blistering rates of the beryllium and beryllide samples were also compared. These results may provide a preliminary experimental basis for evaluating the irradiation swelling resistance of beryllium alloy. Full article
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11 pages, 5221 KB  
Article
Swelling of Highly Neutron Irradiated Beryllium and Titanium Beryllide
by Vladimir Chakin, Alexander Fedorov, Ramil Gaisin and Milan Zmitko
J. Nucl. Eng. 2022, 3(4), 398-408; https://doi.org/10.3390/jne3040026 - 28 Nov 2022
Cited by 12 | Viewed by 2742
Abstract
The swelling of beryllium and titanium beryllide after irradiation at 70–750 °C to neutron fluences of (0.25–8) · 1022 cm−2 (E > 1 MeV) was measured using methods of immersion, dimension, and helium pycnometry. Dependences of the swelling on the irradiation [...] Read more.
The swelling of beryllium and titanium beryllide after irradiation at 70–750 °C to neutron fluences of (0.25–8) · 1022 cm−2 (E > 1 MeV) was measured using methods of immersion, dimension, and helium pycnometry. Dependences of the swelling on the irradiation temperature and neutron dose were plotted and analyzed. The dose dependences show linear dependences of the swelling for all irradiation temperatures except 70 °C, where the swelling rate varies, depending on increasing neutron dose. Be-7Ti shows much less swelling than pure Be. Irradiation at 430–750 °C to neutron fluence of 1.82 · 1022 cm−2 (E > 1 MeV) leads to swelling of Be at about 50%; for Be-7Ti, it is 2.7%. The microstructure study shows that the formation of bubbles and pores in beryllium occurs much more intense than in titanium beryllide. Full article
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