Tritium breeding mock-up experiments containing lithium titanate ceramic pebbles and lead irradiated with DT neutrons

Jakhar, S.; Abhangi, M.; Tiwari, Sanat Kumar; Makwana, R.; Chaudhari, V.; Swami, H.L.; Danani, Chandan; Rao, C. V. S.; Basu, T.K.; Mandal, D.; Bhade, S. P. D.; Kolekar, R.V.; Reddy, Priyanka J.; Bhattacharyay, R.; Chaudhuri, Paritosh

doi:10.1016/j.fusengdes.2015.04.003

Cited by 15 publications

(4 citation statements)

References 15 publications

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“…In recent decades, the demand for lithium has increased substantially on a worldwide scale, mainly driven by the critical role of which lithium plays in the modern materials industry (Al‐Li alloys, polymers, ceramics, and lubricants), nuclear fusion, pharmaceuticals, and especially lithium‐ion batteries. [ 1‐6 ] 65% of the global Li resource was stored in brines, [ 7 ] which became the main source of lithium. Li + separation from the salt lake in China, however, was difficult due to the low concentration of Li + and the characteristically high magnesium/lithium concentration ratio.…”

Section: Background and Originality Contentmentioning

confidence: 99%

Efficient Extraction of Lithium Ions from High Mg/Li Ratio Brine through the Synergy of TBP and Hydroxyl Functional Ionic Liquids

et al. 2020

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of main observation and conclusion The extraction of Li + from the high Mg/Li ratio brine was performed using hydroxyl functional ionic liquids (ILs) as the coextractant and tributyl phosphate (TBP) as the extractant. Firstly, the extractive system, 1-(2-hydroxyethyl)-3-methylimidazolium bis(trifluoromethylsulfonyl)imide ([HOEmim][NTf2]) + TBP was proved to exhibit the highest extraction efficiency of Li + (88.15%) from LiCl aqueous solutions among the extractants composed of different ILs, TBP, and ILs + TBP. Effects of various extraction parameters on the extraction efficiencies of Li + and Mg 2+ were then investigated. 95.01% of Li + was extracted and the Li/Mg separation factor reached 405.76 in a single-stage at 278.15 K and O/A of 2 : 1. The extraction complexes were determined by the slope analysis method and ESI-MS analysis, and the metal complexes in the organic phase were indicated to be mainly [Li•2 TBP][NTf2]. The striping study showed that 92.86% of Li + was stripped with 1.0 mol•L-1 HCl. 98% extraction capacity of the synergy extractants was remained after 5 regeneration cycles. The thermodynamic parameters (ΔG°, ΔH°, and ΔS°), together with the mechanism of the Li + extraction were further demonstrated finally. According to the results, [HOEmim][NTf2] + TBP extraction system showed promising performance in extracting lithium from salt lake brine with high Mg/Li ratio.

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Section: Background and Originality Contentmentioning

confidence: 99%

Efficient Extraction of Lithium Ions from High Mg/Li Ratio Brine through the Synergy of TBP and Hydroxyl Functional Ionic Liquids

et al. 2020

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“…Promoting the utilization of nuclear and thermonuclear energy, and elevating their contribution in the energy sector, offers solutions to a range of challenges, addressing not just energy deficits but also contributing to environmental enhancements-a pivotal objective for future generations. To obtain tritium, which is used as one of the most promising types of fuel for maintaining thermonuclear reactions, lithium-containing ceramics based on titanates, zirconates, or orthosilicates are used, the use of which makes it possible to obtain tritium through nuclear reactions of lithium with neutrons [3][4][5].…”

Section: Introductionmentioning

confidence: 99%

Study of the Surface-Layer Softening Effects in xLi2ZrO3–(1−x)Li4SiO4 Ceramics under Irradiation with He2+ Ions

Shlimas,

Borgekov,

Kadyrzhanov

et al. 2024

Ceramics

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The study investigates alterations in the mechanical and thermophysical properties of ceramics composed of xLi2ZrO3–(1−x)Li4SiO4 as radiation damage accumulates, mainly linked to helium agglomeration in the surface layer. This research is motivated by the potential to develop lithium-containing ceramics characterized by exceptional strength properties and a resistance to the accumulation of radiation damage and ensuing deformation distortions in the near-surface layer. The study of the radiation damage accumulation processes in the near-surface layer was conducted through intense irradiation of ceramics using He2+ ions at a temperature of 700 °C, simulating conditions closely resembling operation conditions. Following this, a correlation between the accumulation of structural modifications (value of atomic displacements) and variations in strength and thermophysical characteristics was established. During the research, it was observed that two-component ceramics exhibit significantly greater resistance to external influences and damage accumulation related to radiation exposure compared to their single-component counterparts. Furthermore, the composition that provides the highest resistance to softening in two-component ceramics is an equal ratio of the components of 0.5Li2ZrO3–0.5Li4SiO4 ceramics.

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“…As its neutron yield is significantly low compared with accelerator-based neutron sources, detectors with ultra-high sensitivity are required [11,12]. One direct method for measuring bred tritium is to count β-rays of irradiated Li 2 CO 3 diagnostic pellets using a liquid scintillation counter (LSC), which evaluates TPR with uncertainties of 4%-10% at the 1σ level [4][5][6][13][14][15]. But, the method is inapplicable for the compact neutron source because the amount of bred tritium would be below the detection limit of LSC with a reasonable operation period.…”

Section: Introductionmentioning

confidence: 99%

Evaluation of tritium production rate in a blanket mock-up using a compact fusion neutron source

et al. 2021

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We report a neutronics study of a blanket mock-up using a discharge-type compact fusion neutron source. Deuterium-deuterium fusion neutrons were irradiated to the mock-ups composed of tritium breeder and neutron reflector/moderator. The tritium production rate (TPR) per source neutron was measured by a single-crystal diamond detector with a 6 Li-enriched lithium fluoride film convertor after the calibration process. Despite the low neutron yield, energetic alpha and triton particles via 6 Li(n, t)α neutron capture as well as 12 C via elastic scattering were successfully detected by the SDD with high signal to noise ratios. The TPRs were experimentally evaluated with errors of 8.4%-8.5% at the 1σ level at the positions with high thermal neutron fluxes where the errors were dominantly introduced by uncertainties in the monitoring of the neutron production rate. The calculated to experimental (C/E) values of TPR were evaluated to be 0.91-1.27 (FENDL-2.1) and 0.94-1.28 (FENDL-3.1). As the neutron source can generate 14 MeV neutrons using a mixed gas of deuterium and tritium, this approach provides more opportunities for blanket neutronics experiments.

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Tritium breeding mock-up experiments containing lithium titanate ceramic pebbles and lead irradiated with DT neutrons

Cited by 15 publications

References 15 publications

Efficient Extraction of Lithium Ions from High Mg/Li Ratio Brine through the Synergy of TBP and Hydroxyl Functional Ionic Liquids

Efficient Extraction of Lithium Ions from High Mg/Li Ratio Brine through the Synergy of TBP and Hydroxyl Functional Ionic Liquids

Study of the Surface-Layer Softening Effects in xLi2ZrO3–(1−x)Li4SiO4 Ceramics under Irradiation with He2+ Ions

Evaluation of tritium production rate in a blanket mock-up using a compact fusion neutron source

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