6533b7dafe1ef96bd126ea81

RESEARCH PRODUCT

Study of tritium and helium generation and release from lead-lithium eutectics Li15.7Pb under neutron irradiation

I. TazhibayevaEvgeny NesterovTimur KulsartovZhanna ZaurbekovaNatalia Valerievna VarlamovaGunta KizaneYuriy PonkratovV. S. Gnyrya

subject

Materials scienceMechanical EngineeringRadiochemistrychemistry.chemical_element01 natural sciences010305 fluids & plasmasFlux (metallurgy)Nuclear Energy and Engineeringchemistry0103 physical sciencesGeneral Materials ScienceLithiumTritiumResearch reactorIrradiation010306 general physicsLead (electronics)HeliumCivil and Structural EngineeringEutectic system

description

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 T2 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.

yearjournalcountryeditionlanguage
2019-09-01Fusion Engineering and Design
https://doi.org/10.1016/j.fusengdes.2019.02.066