Tritium behavior in lithium ceramics

Johnson, Carl E.

doi:10.1016/s0022-3115(98)00905-2

Cited by 85 publications

(55 citation statements)

References 45 publications

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“…The most commonly employed methods are wet process, sol-gel process and mixing of the two oxides followed by compaction and sintering [10][11][12][13][14][15]. The work performed in the last two decades in this field has been reviewed by Johnson [18][19][20][21][22][23][24][25].…”

Section: Introductionmentioning

confidence: 99%

Synthesis & fabrication of lithium-titanate pebbles for ITER breeding blanket by solid state reaction & spherodization

Mandal

Shenoi

Ghosh

2010

Fusion Engineering and Design

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Section: Introductionmentioning

confidence: 99%

Synthesis & fabrication of lithium-titanate pebbles for ITER breeding blanket by solid state reaction & spherodization

Mandal

Shenoi

Ghosh

2010

Fusion Engineering and Design

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“…[6][7][8] The lithium based ceramics, such as Li 2 SiO 4 , have been considered as the favorable candidates of tritium breeders in helium cooled solid pebble bed (HCSPB) design. [9][10][11][12][13][14][15][16][17][18][19][20][21][22] Specially, the lithium orthosilicate (Li 4 SiO 4 ) have the attractive natural characters of high melting temperature, high lithium density, compatibility with the structure materials, tritium release performance and so forth.…”

Section: Introductionmentioning

confidence: 99%

Density functional theory calculations of point defects and hydrogen isotopes in Li4SiO4

Xiang

Zhu

et al. 2015

AIP Advances

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The Li 4 SiO 4 is a promising breeder material for future fusion reactors. Radiation induced vacancies and hydrogen isotope related impurities are the major types of point defects in this breeder material. In present study, various kinds of vacancies and hydrogen isotopes related point defects in Li 4 SiO 4 are investigated through density functional theory (DFT) calculations. The band gap of Li 4 SiO 4 is determined by UVVis diffuse reflectance spectroscopy experiments. Formation energies of all possible charge states of Li, Si and O vacancies are calculated using DFT methods. Formation energies of possible charge states of hydrogen isotopes substitution for Li and O are also calculated. We found that Li-vacancies will dominate among all vacancies in neutral charge state under radiation conditions and the O, Li, and Si vacancies (V O ,V Li ,V Si ) are stable in charge states +2, -1, -4 for most of the range of Fermi level, respectively. The interstitial hydrogen isotopes (H i ) and substitutional H Li are stable in the charge states +1, 0 for most of the range of Fermi level, respectively. Moreover, substitutional H O are stable in +1 charge states. We also investigated the process of tritium recovery by discussing the interaction between interstitial H and Li-vacancy, O-vacancy, and found that H + O and H 0 Li are the most common H related defects during radiation process. C 2015 Author(s). All article content, except where otherwise noted, is licensed under a Creative Commons Attribution 3.0 Unported License. [http://dx

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“…One of the main tasks for this material is the comprehension of Tritium mobility dynamics under reactor work conditions. T mobility inside BB should involve several processes, such as intragranular diffusion, transport along grain boundaries to the pore network, desorption at the gas/solid interface and release to the purge gas flow [ 5 ]. The understanding of Tritium release mechanisms is necessary for reducing T retention in the irradiated matrix.…”

Section: Introductionmentioning

confidence: 99%

3He Behaviour in Li2TiO3 Ceramics for Fusion Breeding Blanket Applications

Carella

González

2013

Energy Procedia

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After Li-transmutation in fusion breeder blanket (BB) materials, T and 4 He will diffuse reaching the breeder surface where will be desorbed. Considering the experimental difficulty of handling T, other light ions are chosen to simulate T behaviour. In the present work, 3 He was implanted to a fluence of 2*10 16 at/cm 2 at -120ºC using a 600 keV 3 He beam on sintered Li 2 TiO 3 ceramics, one of the best candidates as BB solid materials. Temperature was increased up to 900 ºC and the 3 He release curve registered during heating. The 3 He depth profiling is then obtained at -120ºC, after 1h of annealing at 150 ºC, and finally after 5min at the maximum temperature (900 ºC) using NR analysis. A previous work on D-depth thermal profiling reveals the importance of the matrix microstructural characteristics. Therefore both experiments are discussed comparatively.

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Tritium behavior in lithium ceramics

Cited by 85 publications

References 45 publications

Synthesis & fabrication of lithium-titanate pebbles for ITER breeding blanket by solid state reaction & spherodization

Synthesis & fabrication of lithium-titanate pebbles for ITER breeding blanket by solid state reaction & spherodization

Density functional theory calculations of point defects and hydrogen isotopes in Li4SiO4

3He Behaviour in Li2TiO3 Ceramics for Fusion Breeding Blanket Applications

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