Results 61 to 70 of about 8,401 (181)

HICU PIE results of neutron-irradiated lithium metatitanate pebbles

open access: yesNuclear Materials and Energy
Lithium metatitanate (Li2TiO3) pebbles were irradiated with neutrons within the HICU (High neutron fluence Irradiation of pebble staCks for fUsion) experiment to investigate their material properties and tritium release behaviour in a post-irradiation ...
Julia Leys   +3 more
doaj   +1 more source

Study on the radiological effect of the tritium gas released from fussion reactor

open access: yesHe jishu
BackgroundThe amount of gaseous tritium stored and released in fusion reactor is higher than that in current fission reactors, so that tritium is an important source of potential radioactivity in fusion reactor.PurposeThis study aims to investigate the ...
ZUO Qingning   +5 more
doaj   +1 more source

Estimation and Mode Selection of Deuterium Flux Supply into Ampoule Device Through Diffusion Filter in Experiments with Pb15.7Li Eutectic at the IVG1.M Reactor

open access: yesEurasian Chemico-Technological Journal, 2019
One of the most promising materials to produce tritium in fuel cycle of fusion facilities is the lead-lithium eutectic Pb15.7Li. Tritium will be generated in nuclear reactions in a lithium-containing material under the influence of neutron irradiation ...
Ye. Tulubayev   +4 more
doaj   +1 more source

Determination of tritium inventory in carbon divertor tiles used in deuterium plasma experiment by induction heating method

open access: yesNuclear Materials and Energy
The tritium inventory of the plasma-facing materials in a Large Helical Device (LHD) was analyzed using a thermal desorption system. In this study, we developed an induction heating system for the thermal desorption of tritium from carbon divertor tiles,
Masahiro Tanaka   +5 more
doaj   +1 more source

Features of Helium and Tritium Release from Li2TiO3 Ceramic Pebbles under Neutron Irradiation. [PDF]

open access: yesMaterials (Basel), 2023
Kulsartov T   +8 more
europepmc   +1 more source

Research on the optimization method of tritium release efficiency in a water cooled blanket for CFETR

open access: yesAIP Advances
The Chinese Fusion Engineering Test Reactor (CFETR) is a tokamak device located between ITER and DEMO, with the primary goal of generating useable fusion energy through D–T reactions.
Jie Li   +4 more
doaj   +1 more source

TGA study of high-temperature corrosion behavior of neutron-irradiated Be12Ti in the presence of water vapor

open access: yesNuclear Materials and Energy
This paper investigates the high-temperature corrosion of neutron-irradiated titanium beryllide Be12Ti in a vapor-argon environment, emphasizing the kinetics of mass loss and the forms of released tritium.
Asset Shaimerdenov   +9 more
doaj   +1 more source

Synthesis of [24, 25-3H]cholesterol: a new substrate for determining the rate of cholesterol side chain oxidation.

open access: yesJournal of Lipid Research, 1979
A procedure for the synthesis of [24,25-3H]cholesterol from the nonradioactive precursor desmosterol is described. The intermediate, isodesmosterol, which was purified by column chromatography, was formed to protect the original double bond (delta 5-6 ...
C L Bentzen, K Brendel
doaj   +1 more source

Development and validation of a program for assessing the consequences of radioactivity releases from fusion reactor accidents

open access: yesFushe yanjiu yu fushe gongyi xuebao
The deuterium-tritium fusion reaction is the fastest commercially achievable artificially controlled fusion reaction. However, tritium, as a fuel and neutron radiation-activated material, poses radioactive safety challenges.
CUI Weijie   +3 more
doaj   +1 more source

Tritium Release from Improved Ceramic Tritium Breeder with Catalytic Function [PDF]

open access: yesJournal of Nuclear Science and Technology, 1999
Kenzo MUNAKATA   +9 more
openaire   +1 more source

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