Results 1 to 10 of about 8,377 (163)
Nuclear Materials and Energy, 2016 Study of tritium and helium release from beryllium pebbles with diameters of 0.5 and 1mm after high-dose neutron irradiation at temperatures of 686–968K was performed.
Vladimir Chakin +3 more
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Nuclear Materials and Energy, 2016 Lithium titanate with excess lithium (Li2+xTiO3+y) is one of the most promising candidates among advanced tritium breeders for demonstration power plant reactors because of its good tritium release characteristics.
Tsuyoshi Hoshino
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Estimation of tritium generation and discharge of the AP1000 reactor based on historical discharge data from the U.S. Pressurized water reactors [PDF]
Nuclear Technology and Radiation Protection, 2023 During the normal operation of pressurized water reactors, tritium has contributed more than 95 % of the total radioactivity of all the radionuclides discharged into the environment and has been recognized as the key radionuclide in the design ...
Wang Qi
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Investigation on effects of tritium release behavior in Li4SiO4 pebbles
Nuclear Materials and Energy, 2021 For deuterium–tritium fusion reactor, the fuel of tritium is not available naturally. Tritium should be produced by the reaction of Li (n, ɑ) T. Li4SiO4 is one of promising candidates due to its high lithium density.
Qiang Qi +9 more
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Nuclear Analysis, 2023 In order to have a deep understanding of the tritium migration and release mechanisms in ceramic breeders, computer simulation of the tritium release behavior of Li4SiO4 ceramic breeder was performed by using an improved tritium release model.
Guangming Ran +3 more
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Inversion of tritium source term based on adaptive Kalman filter and deep feedforward neural network
Fushe yanjiu yu fushe gongyi xuebao, 2023 Deuterium （D） and tritium （T） have been regarded as the first-generation fuels for achieving commercial fusion energy. However， the utilization of the radionuclide tritium introduces concerns related to radioactive safety.
ZHANG Jinlong, CUI Weijie, LI Zaixin
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Simulation study of tritium atmospheric dispersion of loss of vacuum accident of a fusion reactor
He jishu, 2023 BackgroundTritium can be released into the environment in a loss of vacuum (LOVA) scenario in a fusion reactor. The simulation of the atmospheric dispersion behaviour of tritium is one of the core components of the assessment of the radioactive ...
JIANG Jinghua, CAO Xuewu
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Nuclear Materials and Energy, 2023 Biphasic lithium ceramics based on lithium orthosilicate Li4SiO4 and lithium metatitanate Li2TiO3 is one of the most promising materials for breeder blankets of future fusion reactors.
Timur Kulsartov +10 more
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Nuclear Materials and Energy, 2022 This paper analyzes part of the reactor experiments on the study of tritium and helium release from promising two-phase lithium ceramic (Li2TiO3 and Li4SiO4) of natural lithium enrichment conducted by vacuum extraction.The basis for such an analysis was ...
Inesh Kenzhina +12 more
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Nuclear Materials and Energy, 2022 In the development of fusion energy, an important task is the study and improvement of tritium production technologies. In this case, one of the most promising materials for tritium generation is lithium ceramics.
Timur Kulsartov +13 more
doaj +1 more source