Abstract
This paper describes the experiments on study of tritium and helium generation and release processes from lead-lithium eutectics Li15.7Pb. The irradiation was performed at the IVG.1M research reactor at 6 MW of thermal power. The irradiation temperature increased step by step from 225 to 550 °C. A qualitative assessment of the experimental results showed that as the temperature rises above 390 °C, the tritium flux from the sample consisting of T 2 and HT molecules decreases. It was concluded that the observed effect is similar to the previously observed one for lead-lithium eutectics with Li17Pb83 composition.
| Original language | English |
|---|---|
| Journal | Fusion Engineering and Design |
| DOIs | |
| Publication status | Published - 1 Jan 2019 |
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Keywords
- Helium
- Lead-Lithium eutectics
- Neutron irradiation
- Tritium
ASJC Scopus subject areas
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering
Cite this
Study of tritium and helium generation and release from lead-lithium eutectics Li15.7Pb under neutron irradiation. / Kulsartov, Timur; Zaurbekova, Zhanna; Tazhibayeva, Irina; Ponkratov, Yuriy; Gnyrya, Vyacheslav; Kizane, Gunta; Nesterov, Evgeny; Varlamova, Natalia.
In: Fusion Engineering and Design, 01.01.2019.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Study of tritium and helium generation and release from lead-lithium eutectics Li15.7Pb under neutron irradiation
AU - Kulsartov, Timur
AU - Zaurbekova, Zhanna
AU - Tazhibayeva, Irina
AU - Ponkratov, Yuriy
AU - Gnyrya, Vyacheslav
AU - Kizane, Gunta
AU - Nesterov, Evgeny
AU - Varlamova, Natalia
PY - 2019/1/1
Y1 - 2019/1/1
N2 - This paper describes the experiments on study of tritium and helium generation and release processes from lead-lithium eutectics Li15.7Pb. The irradiation was performed at the IVG.1M research reactor at 6 MW of thermal power. The irradiation temperature increased step by step from 225 to 550 °C. A qualitative assessment of the experimental results showed that as the temperature rises above 390 °C, the tritium flux from the sample consisting of T 2 and HT molecules decreases. It was concluded that the observed effect is similar to the previously observed one for lead-lithium eutectics with Li17Pb83 composition.
AB - This paper describes the experiments on study of tritium and helium generation and release processes from lead-lithium eutectics Li15.7Pb. The irradiation was performed at the IVG.1M research reactor at 6 MW of thermal power. The irradiation temperature increased step by step from 225 to 550 °C. A qualitative assessment of the experimental results showed that as the temperature rises above 390 °C, the tritium flux from the sample consisting of T 2 and HT molecules decreases. It was concluded that the observed effect is similar to the previously observed one for lead-lithium eutectics with Li17Pb83 composition.
KW - Helium
KW - Lead-Lithium eutectics
KW - Neutron irradiation
KW - Tritium
UR - http://www.scopus.com/inward/record.url?scp=85061776595&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85061776595&partnerID=8YFLogxK
U2 - 10.1016/j.fusengdes.2019.02.066
DO - 10.1016/j.fusengdes.2019.02.066
M3 - Article
AN - SCOPUS:85061776595
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
SN - 0920-3796
ER -