Results 71 to 80 of about 209 (131)

Adsorption characteristics of tritium in lithium vacancy for Li4SiO4: A density functional theory study

open access: yesNuclear Engineering and Technology
Lithium orthosilicate (Li4SiO4) is a promising breeder material with its high lithium density and low tritium retention for fusion reactor blanket. After neutron irradiation, Li4SiO4 not only produces tritium but also forms lithium vacancy defects, which
Siman Li   +6 more
doaj   +1 more source

Aging Effects in Zr(Fe0.5V0.5)2 Tritides

open access: yesCrystals
We report an experimental study on the tritiding capabilities over a long period of the intermetallic compound Zr(Fe0.5V0.5)2. The study was carried out with the prospect of using the alloy as a chemical converter to reduce HTO. Two identical getter beds,
Francesco Ghezzi   +1 more
doaj   +1 more source

Studies of irradiated two-phase lithium ceramics Li4SiO4/Li2TiO3 by thermal desorption spectroscopy

open access: yesNuclear Materials and Energy
Two-phase ceramics Li2TiO3-Li4SiO4 are one of the potentially promising materials for creating a ceramic blanket for DEMO reactor. However, until now, a limited number of studies have been carried out on the release of tritium from this material under ...
Yevgen Chikhray   +12 more
doaj   +1 more source

Research progress in production of tritium breeding lithium ceramics for nuclear fusion

open access: yesCailiao gongcheng
Lithium ceramics (e.g.,Li4SiO4,Li2TiO3),as core tritium breeder materials, possess high lithium density, excellent thermal stability, and irradiation resistance.
CHEN Zhangwei   +6 more
doaj   +1 more source

Tritium content in water bodies in regions of peaceful nuclear explosions

open access: yesРадиационная гигиена
Sites of peaceful nuclear explosions pose a potential radiation hazard to the territories of the Russian Federation, primarily due to the possible release of radioactivity from the explosion cavity into aquifers and onto the earth's surface.
V. S. Repin   +5 more
doaj   +1 more source

In-situ methodology for studying tritium and helium-4 release processes from gallium-lithium alloy under irradiation at a research nuclear reactor

open access: yesNuclear Materials and Energy
This paper presents an in-situ methodology for studying the kinetics of tritium and helium-4 release from the intermetallic alloy Ga64Li36 during continuous neutron irradiation at the IVG.1 M research nuclear reactor.
Yu. Ponkratov   +8 more
doaj   +1 more source

Release of tritium from tritiated paints

open access: yes, 1974
A study of the tritium losses from five tritiated phosphor paints showed that the losses from these paints were generally low. Samples of five different paints which were leach tested six times over a period of 11 months had losses ranging from 0.018 to 0.731% of the initial activity in the samples. Tritium evolved from a paint which had been cured for
openaire   +2 more sources

Tritium Confinement, Retention, and Releases at the Tritium Laboratory Karlsruhe

Fusion Science and Technology, 2008
This paper describes the tritium confinement concept and the tritium retention systems at TLK. A description of the AMOR facility for the regeneration of the HTO loaded molecular sieve beds and the operational experience gained from the regeneration of molecular sieve beds (up to 20 times each) is also presented.
Besserer, U., Dörr, L., Glugla, M.
openaire   +2 more sources

Tritium levels in milk in the vicinity of chronic tritium releases

Journal of Environmental Radioactivity, 2016
Tritium is the radioactive isotope of hydrogen. It can be integrated into most biological molecules. Even though its radiotoxicity is weak, the effects of tritium can be increased following concentration in critical compartments of living organisms. For a better understanding of tritium circulation in the environment and to highlight transfer constants
Le Goff, Pierre   +6 more
openaire   +3 more sources

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