Results 71 to 80 of about 9,941 (218)
HICU PIE results of neutron-irradiated lithium metatitanate pebbles
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
In this work, the electrochemical compatibility of a broad range of solid polymer electrolytes with two Ni‐rich nickel–manganese–cobalt cathodes (NMC622, NMC811) is investigated through a hybrid computational and experimental approach. The relative reactivity of NMC811 to NMC622 is demonstrated, as well as the role of Li cations in the electrolyte ...
Alexandre Roelens +9 more
wiley +1 more source
Tritium transport and release from lithium ceramic breeder materials
In an operating fusion reactor,, the tritium breeding blanket will reach a condition in which the tritium release rate equals the production rate. The tritium release rate must be fast enough that the tritium inventory in the blanket does not become ...
Tam, S. W. +2 more
core
The "In-pile tritium-release experimental apparatus" was designed and installed at JRR-4 in order to study tritium release from UO2 during reactor operation. It mainly consists of three systems: the irradiation rig, the gas-supplying system and the tritium-collecting system.
Yasuyuki ARATONO +3 more
openaire +3 more sources
Study on the radiological effect of the tritium gas released from fussion reactor
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
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
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
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
Features of Helium and Tritium Release from Li2TiO3 Ceramic Pebbles under Neutron Irradiation. [PDF]
Kulsartov T +8 more
europepmc +1 more source
An atmospheric tritium release database for model comparisons [PDF]
A database of vegetation, soil, and air tritium concentrations at gridded coordinate locations following nine accidental atmospheric releases is described.
Murphy, C. E. Jr., Wortham, G. R.
core +1 more source

