Tritium and helium release from highly neutron irradiated titanium beryllide

Chakin, V.; Rolli, R.; Moeslang, A.; Kurinskiy, P.

doi:10.1016/j.fusengdes.2015.01.038

Cited by 18 publications

(4 citation statements)

References 12 publications

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“…It was also determined that in beryllium of S-65C and S-200F grades a significantportion of tritium and helium is releasedonly during melting. Similar results were obtained in [5].…”

Section: Aadvantages Of Titanium Beryllide Over Berylliumsupporting

confidence: 90%

“…Release of tritium and helium from beryllium after irradiation at 370°C (743K) when heated at a rate of 7K/min. [5] It follows that temperature of release of tritium and helium produced in the process of neutron irradiation from beryllium is much higher than the temperature limit of its operation.…”

Section: Aadvantages Of Titanium Beryllide Over Berylliummentioning

confidence: 99%

“…Figure 2.Release of tritium and helium from beryllium after irradiation at 370°C (743K) when heated at a rate of 7K/min [5]. …”

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confidence: 99%

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Titanium beryllide as an alternative to beryllium in nuclear and thermonuclear engineering, capabilities of UMP JSC in the technology development and beryllides products manufacture

Frants¹,

Borsuk²,

Vechkutov³

et al. 2022

J. Phys.: Conf. Ser.

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For many decades, beryllium has been used as a structural element in nuclear installations as a moderator / breeder of fast neutrons. The consequence of neutron irradiation is a significant production of gas products in the form of helium and tritium, which leads to swelling and loss of strength properties of beryllium reflectors. The relatively low melting point of beryllium also imposes restrictions on the high-limit temperature regimes of the reactor core. As an alternative to pure beryllium, it is necessary to consider intermetallic compounds based on it, in particular titanium beryllide. Preliminary studies on the thermal desorption of helium and tritium from titanium beryllide have shown that this material has a much lower retention tendency and a lower release temperature. The higher melting point of titanium beryllide compared to pure beryllium is also an advantageous characteristic.Over the past years, UMP JSC, thanks to its research in this area, has achieved significant success in the development of technology for obtaining intermetallic billets and articles based on titanium and chromium beryllides. As a technology demonstrator, prototypes of structural elements of a helium-cooled blanket breeder module of the projected DEMO reactor were made by order of the Karlsruhe Institute of Technology, Germany.The advantages of titanium beryllide, as well as the success achieved in the production of billets and products from it, open up opportunities for a more extensive study of the nuclear, physical and mechanical properties of this material with the possibility of further use in nuclear technology, including thermonuclear reactors, and in high-temperature instrumentation.

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“…It was also determined that in beryllium of S-65C and S-200F grades a significantportion of tritium and helium is releasedonly during melting. Similar results were obtained in [5].…”

Section: Aadvantages Of Titanium Beryllide Over Berylliumsupporting

confidence: 90%

Section: Aadvantages Of Titanium Beryllide Over Berylliummentioning

confidence: 99%

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Titanium beryllide as an alternative to beryllium in nuclear and thermonuclear engineering, capabilities of UMP JSC in the technology development and beryllides products manufacture

Frants¹,

Borsuk²,

Vechkutov³

et al. 2022

J. Phys.: Conf. Ser.

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“…[1][2][3] To date, only a few irradiation experiments on Be 12 Ti have been performed. [4][5][6] Bubbles were observed in Be 12 Ti after neutron irradiation at high temperatures, and the swelling was estimated to be 0.006 and 0.02% dpa À1 at 740 and 873 K, respectively. [5] In addition, antisite defects can be formed during irradiation.…”

Section: Introductionmentioning

confidence: 99%

Study of Vacancy Clusters and Antisite Defects in Titanium Beryllide Be₁₂Ti Using Positron Annihilation Spectroscopy

Xu,

Yang,

Popov

et al. 2024

Physica Status Solidi (b)

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Beryllium (Be) intermetallic compounds (beryllides) are promising materials for neutron multiplication in fusion reactors. In particular, titanium beryllide (Be12Ti) exhibits low swelling and good corrosion resistance compared to other beryllides. Herein, the defects in neutron‐irradiated Be12Ti are investigated using positron annihilation spectroscopy, and the results are analyzed based on positron annihilation calculations. Calculation results indicate that the positron lifetime in a perfect Be12Ti crystal is 134.2 ps, while that of a Be monovacancy is found to be within the 177.3–195.0 ps range, depending on the configuration of the monovacancy. On the other hand, the positron lifetime of the Ti monovacancy is 222.7 ps. In addition, the lifetimes of the Be and Ti vacancy clusters increase with an increase in the number of vacancies. Finally, the positron lifetimes of the antisite defects in different configurations are found to be within the 137.9–141.7 ps range. In contrast to the calculated results, the positron lifetime of unirradiated Be12Ti is 141.1 ps. Furthermore, in the neutron‐irradiated Be12Ti, no vacancies are detected and only Be dislocation loop formation occur based on the calculation results. Although the irradiation dose of Be12Ti is low, its irradiation resistance is satisfactory.

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Optimization on producibility improvement and the recycling process of neutron multipliers for fusion applications

Kim

Nakamichi

2019

J Mater Sci

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Tritium and helium release from highly neutron irradiated titanium beryllide

Cited by 18 publications

References 12 publications

Titanium beryllide as an alternative to beryllium in nuclear and thermonuclear engineering, capabilities of UMP JSC in the technology development and beryllides products manufacture

Titanium beryllide as an alternative to beryllium in nuclear and thermonuclear engineering, capabilities of UMP JSC in the technology development and beryllides products manufacture

Study of Vacancy Clusters and Antisite Defects in Titanium Beryllide Be₁₂Ti Using Positron Annihilation Spectroscopy

Optimization on producibility improvement and the recycling process of neutron multipliers for fusion applications

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Tritium and helium release from highly neutron irradiated titanium beryllide

Cited by 18 publications

References 12 publications

Titanium beryllide as an alternative to beryllium in nuclear and thermonuclear engineering, capabilities of UMP JSC in the technology development and beryllides products manufacture

Titanium beryllide as an alternative to beryllium in nuclear and thermonuclear engineering, capabilities of UMP JSC in the technology development and beryllides products manufacture

Study of Vacancy Clusters and Antisite Defects in Titanium Beryllide Be12Ti Using Positron Annihilation Spectroscopy

Optimization on producibility improvement and the recycling process of neutron multipliers for fusion applications

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Study of Vacancy Clusters and Antisite Defects in Titanium Beryllide Be₁₂Ti Using Positron Annihilation Spectroscopy