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The HICU PIE Results of EU Ceramic Breeder Pebbles: Tritium Release Properties

Journal of Nuclear Materials, 2020
The former EU reference lithium orthosilicate based breeder pebbles were exposed to neutron irradiation in the HICU (High neutron fluence Irradiation of pebble staCks for fUsion) experiment to test their stability and tritium release properties under ...
Regina Knitter, R Rolli, M Zmítko
exaly   +2 more sources

Tritium release behavior of Li2TiO3 and 2Li2TiO3-Li4SiO4 biphasic ceramic pebbles fabricated by microwave sintering

Fusion engineering and design, 2021
Li2TiO3-Li4SiO4 biphasic ceramic is considered as an advanced tritium breeder material for its potential to combine the advantages of both Li2TiO3 and Li4SiO4.
Mao Yang   +8 more
semanticscholar   +1 more source

Characterization of Li-rich Li2TiO3 ceramic pebbles prepared by rolling method sintered in air and vacuum

, 2021
Li2TiO3 with excess Li was developed as an advanced tritium breeder material for fusion reactors. To improve tritium release performance, the breeder pebbles should have a uniform microstructure with small grains.
Hao Guo   +8 more
semanticscholar   +1 more source

Assessment of the chemical compatibility between EUROFER and ceramic breeder with respect to fatigue lifetime

Fusion engineering and design, 2020
In advanced designs of DEMO breeding blankets with ceramic breeder, the structural material EUROFER is in direct contact with the pebbles of the ceramic breeder (Li4SiO4 + Li2TiO3) that results in a loss of constituent elements in the ceramic and the ...
J. Aktaa   +4 more
semanticscholar   +1 more source

Compatibility of tritium permeation barrier coatings with ceramic breeder pebbles

, 2021
Reduced activation ferritic/martensitic steel F82H samples with tritium permeation barriers were annealed in contact with ceramic breeder pebbles at 550 °C and 700 °C for up to 32 days under purge gas.
T. Chikada   +8 more
semanticscholar   +1 more source

Cyclic behavior of ceramic pebble beds under mechanical loading

Fusion engineering and design, 2018
Uniaxial compression test (UCT) experiments were conducted along with Discrete Element Method (DEM) simulations. The objective was to investigate the effect of the material properties and of the blanket operational parameters (in terms of packing factor,
S. Pupeschi   +4 more
semanticscholar   +1 more source

Mechanical compression behaviors of single phase Be and binary Be12Ti pebbles

Fusion engineering and design, 2019
Beryllium pebbles are planned to be used as a neutron multiplier in the Helium-cooled ceramic breeder (HCCB) tritium breeding blanket module (TBM) of ITER, which is also the primary option of the Chinese TBM program.
P.-P. Liu   +9 more
semanticscholar   +1 more source

Long-term thermal stability of two-phased lithium orthosilicate/metatitanate ceramics

Journal of Nuclear Materials, 2018
The long-term thermal stability of advanced ceramic breeder pebbles consisting of lithium orthosilicate (Li4SiO4) and additions of lithium metatitanate (Li2TiO3) was tested in an annealing experiment at 900 °C for up to 128 days.
J. Heuser   +3 more
semanticscholar   +1 more source

Design of Two Experimental Mock-Ups as Proof-of-Concept and Validation Test Rigs for the Enhanced EU DEMO HCPB Blanket

Fusion science and technology, 2019
Within the framework of EUROfusion activities, the helium cooled pebble bed (HCPB) breeding blanket is under development in Karlsruhe Institute of Technology (KIT).
Guang-Ming Zhou   +4 more
semanticscholar   +1 more source

Radiation-induced effects in neutron- and electron-irradiated lithium silicate ceramic breeder pebbles

, 2020
Ceramic breeder (CB) pebbles consisting of lithium orthosilicate (Li4SiO4) as the main phase and lithium metasilicate (Li2SiO3) as a secondary phase were analysed with respect to radiation-induced defects and radiolysis products.
J. Leys   +5 more
semanticscholar   +1 more source

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