Core configuration of a gas-cooled reactor as a tritium production device for fusion reactor

Nakaya, Hiroyuki; Matsuura, Hideaki; Nakao, Yasuyuki; Shimakawa, Satoshi; Goto, Minoru; Nakagawa, Shigeaki; Nishikawa, Masahiro

doi:10.1016/j.nucengdes.2013.12.023

Cited by 15 publications

(3 citation statements)

References 5 publications

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“…In molten carbonate fuel cells (MCFCs), LiAlO 2 is used as the electrolyte matrix . In fusion energy, LiAlO 2 is a candidate material for producing tritium in a tritium breeder blanket . LiAlO 2 has also been used to produce tritium inside a tritium‐producing‐burnable‐absorber‐rod (TPBAR) in conventional nuclear fission reactors .…”

Section: Introductionmentioning

confidence: 99%

Role of interfaces in damage process of irradiated lithium aluminate nanocrystals

Senor

Devanathan

2018

J Am Ceram Soc

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Molecular dynamics simulations were performed to understand the differences in the response of single crystal and nanocrystalline γ‐LiAlO2 to energy deposition by 10 keV Li recoils. The simulations are performed at 573 K and focus on the damage production in the absence of thermal annealing. The grain boundaries in the nanocrystals are found to be amorphous. Analyses of the fate of the beam ions show that the amorphous grain boundaries and differently oriented nanograins increase the number of backscattered ions and decrease the number of transmitted ions. Damaged regions protruding from the grain boundaries provide a direct evidence of the role of the grain boundaries as scattering centers in collision cascades. The simulations show that the defect density produced in the nanocrystals is about twice that in the single crystals. In both samples, Li defects account for 70% of the defects, demonstrating that LiO4 tetrahedra are much more susceptible to damage than AlO4 tetrahedra. Furthermore, Li defects occur preferentially near grain boundaries. Diffusion simulations confirm the limited thermal diffusion of defects at 573 K, effectively separating the damage production from thermal annealing in the irradiation simulations. Nevertheless, the mean square displacements of grain‐boundary defects are found to be larger than lattice defects and surface defects.

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Section: Introductionmentioning

confidence: 99%

Role of interfaces in damage process of irradiated lithium aluminate nanocrystals

Senor

Devanathan

2018

J Am Ceram Soc

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“…Isotope 6 Li-enriched -LiAlO 2 has been proposed as a promising material for development of neutron dosimeters [1] and has been considered as a candidate for production of tritium in fusion reactor designs [2]. It has also been used as a solid breeder material in support of tritium readiness campaign [3].…”

Section: Introductionmentioning

confidence: 99%

Irradiation effects and hydrogen behavior in H2+ and He+ implanted γ-LiAlO2 single crystals

Jiang

Zhang

Kovařík

et al. 2017

Journal of Nuclear Materials

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Gamma-phase lithium aluminate (-LiAlO 2 ) is a breeder material for tritium, a necessary substance for strategic stockpile and fusion power systems. A fundamental study of structural evolution and tritium diffusion in -LiAlO 2 under displacive irradiation is needed to fully assess the material performance. This study utilizes ion implantation of protium (surrogate for tritium) and helium in -LiAlO 2 single crystals at elevated temperatures to emulate the irradiation effects. The results show that at 573 K there are two distinct disorder saturation stages to 1 dpa without full amorphization; overlapping implantation of H 2 + and He + ions suggests possible formation of gas bubbles. For irradiation to 10 21 H + /m 2 (0.36 dpa at peak) at 773 K, amorphization occurs at surface with H diffusion and dramatic Li loss; the microstructure contains bubbles and cubic LiAl 5 O 8 precipitates with sizes up to 200 nm or larger. In addition, significant H diffusion and release are observed during thermal annealing.

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“…The formation of atomic-level defects and their influence on Li transport in Li-containing ceramics is of great interest for many energy technologies. − In particular, lithium aluminate (LiAlO 2 ) has potential applications in lithium polymer batteries, molten carbonate fuel cells, fusion reactor blankets, − and tritium production using a nuclear reactor . γ-LiAlO 2 , along with Li 2 O, Li 4 SiO 4 , and Li 2 ZrO 3 , is attractive as a solid breeder material for tritium because of good thermophysical and chemical stabilities at elevated temperatures in addition to good tritium release characteristics. , However, the phase stability can be compromised under neutron irradiation.…”

Section: Introductionmentioning

confidence: 99%

Insights on Amorphization of Lithium Aluminate from Atomistic Simulation

Senor

Devanathan

2017

J. Phys. Chem. C

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We simulated amorphization of lithium aluminate by atomic displacement using molecular dynamics to understand the effect of defects on fast lithium ion transport in disordered ceramics. We analyzed the evolution of the AlO4, LiO4, and OLi2Al2 tetrahedral clusters as a function of damage dose calculated in displacements per atom (dpa). The amorphization was associated with the loss of long-range ordering in the network of AlO4 tetrahedra, even though each AlO4 cluster remained tetrahedrally coordinated. The crystalline–amorphous transition occurred gradually within a dose range from 0.1 to 0.2 dpa. The structural damage also induced chemical composition separation, resulting in (Al + O)-rich and Li-rich regions. As a result of the disorder, the Li diffusion coefficient was found to increase to the order of 10–6 cm2/s.

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Core configuration of a gas-cooled reactor as a tritium production device for fusion reactor

Cited by 15 publications

References 5 publications

Role of interfaces in damage process of irradiated lithium aluminate nanocrystals

Role of interfaces in damage process of irradiated lithium aluminate nanocrystals

Irradiation effects and hydrogen behavior in H2+ and He+ implanted γ-LiAlO2 single crystals

Insights on Amorphization of Lithium Aluminate from Atomistic Simulation

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