Effects of radiation on lithium aluminate samples properties

Botter, F.; Lefèvre, Frédéric; Rasneur, B.; Trotabas, M.; Roth, E.

doi:10.1016/s0022-3115(86)80066-6

Cited by 19 publications

(11 citation statements)

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“…Li-containing ceramics have been in the center of study in tritium ( 3 H, T) science and technology as breeding blanket materials for 3 H breeding components in the deuterium–tritium (D–T) fusion reactor. − These materials possess superior thermo-physical and thermo-chemical properties. Among them, lithium zirconate (Li 2 ZrO 3 ) is one of the best candidate blanket materials for tritium breeding components in a D–T fusion reactor. − The 3 H diffusion and recovery processes have been studied experimentally in ceramic breeding materials irradiated with neutron beams by Okuno and Kudo. , It was revealed that the tritium produced in the ceramic materials (Li 2 O, γ-LiAlO 2 , Li 2 SiO 3 , Li 4 SiO 4 , Li 2 ZrO 3 , Li 8 ZrO 6 ) irradiated with neutron beams was released mainly in the chemical form of tritiated water (HTO) when heated in vacuum .…”

Section: Introductionmentioning

confidence: 99%

A First-Principles Density Function Theory Study of Tritium Diffusion in Li₂ZrO₃: Application for Producing Tritium

Paudel

Duan

2018

J. Phys. Chem. C

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The ceramic material Li2ZrO3 has superior thermo-physical and thermo-chemical properties and is highly compatible with other blanket materials used in nuclear reactors. Like LiAlO2, it could be used in the form of an annular pellet in tritium-producing burnable absorber rods (TPBARs) to produce tritium(3H) upon thermal neutron irradiation of lithium isotope (6Li). The radiation damaged pellet crystal contains vacancies, defects of its constituent elements, and several other trapping sites which hinder the 3H diffusion process and releasing behavior. In this study, we investigate the diffusion mechanisms of 3H and O3H species in Li2ZrO3 ceramic pellet in order to understand the effects on diffusion barriers and diffusion coefficients due to the presence of interstitial and substitutional Li defects, hydroxide (O–3H) vacancy defect, and of the interactions of 3H with O-vacancies in the radiation damaged Li2ZrO3 crystal. We consider several possible diffusion pathways of interstitial and substitutional 3H and its species in a defective supercell and calculate the activation energy barrier profiles. We find that the smallest activation energy barrier is 0.3 eV and corresponding diffusion coefficient at 600 K is 1.93 × 10–9 m2/s for 3H substitutional diffusion. The smallest 3H interstitial diffusion barrier and diffusion coefficient are found to be 0.34 eV and 3.25 × 10–9 m2/s. By examining several channels for diffusion, our results show the most likely diffusion mechanism of 3H migration is occurring along the c-direction by exchange of 3H within and between different Li sites. Our calculated results reveal that the smallest energy barrier for O3H diffusion is 0.75 eV which is when O3H is diffusing to the O–Li vacancy pair and the corresponding diffusion coefficient is 6.31 × 10–13 m2/s. In terms of 3H diffusion, the obtained results indicate that the performance of Li2ZrO3 could be better than γ-LiAlO2, a widely used ceramic material in TPBAR for producing 3H.

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Section: Introductionmentioning

confidence: 99%

A First-Principles Density Function Theory Study of Tritium Diffusion in Li₂ZrO₃: Application for Producing Tritium

Paudel

Duan

2018

J. Phys. Chem. C

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“…•Because neutron irradiation continuously changes the composition of the ternary ceramics and induces damage in all ceramic breeders, their properties and behavior can be affected. The irradiation behavior of the ceramic breeders was investigated in both thermal [53] and fast reactors [54].…”

Section: Materials Propertiesmentioning

confidence: 99%

Fabrication, properties, and tritium recovery from solid breeder materials

Johnson

Kondo²,

Roux

et al. 1991

Fusion Engineering and Design

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The breeding blanket is a key component of the fusion reactor because it directly involves tritium breeding and energy extraction, both of which are critical to development of fusion power. The lithium ceramics continue to show promise as candidate breeder materials. This promise was recognized by the International Thermonuclear Experimental Reactor (ITER) design team in its selection of ceramics as the first option for the ITER breeder material. Blanket design studies have indicated properties in the candidate materials data base that need further investigation. Current studies are focusing on tritium release behavior at high burnup, changes in thermophysical properties with burnup, compatibility between the ceramic breeder and beryllium multiplier, and phase changes with burnup. Laboratory and in-reactor tests, some as part of an international collaboration for development of ceramic breeder materials, are underway. Current experimental research is addressing issues identified in ITER blanket design studies, for example, compatibility of the breeder with the beryllium multiplier, tritium release behavior at high burnup, effects of breeder burnup on th£rmophysical properties, and operation at lower temperatures (i.e., <623 K). At present, the design studies place a great emphasis on neutron irradiation effects, and the experimental effort reflects interest in multiple effects. However, complementary separate-effects laboratory experiments are still required to ensure correct interpretation of a material's irradiation behavior. This paper will focus on recent research concerning candidate materials properties, fabrication methodology, irradiation behavior, and tritium transport, as well as computer modeling of tritium transport and release. 2. Materials Preparation and Fabrication In this section the varied processes used to prepare the candidate ceramic breeder material are identified. The powder preparation, fabrication of shapes, and industrial scale production will be discussed. 2.1 Materials Preparation Preparation methods for the ceramic breeders fall into one of three classes, namely: a) solid state reactions, b) solution processes (aqueous or alcohol), and c}-so1-gel methods. Each method, when done properly, yields high purity materials. 2.1.1 Lithium aluminate HAIO2 The standard technique for the synthesis of UAIO2 is the solid state reaction: Li 2 C0 3 + AI2O3 = 2LiAl0 2 + C0 2 (1) This reaction, introduced by Hummel[6], is widely used at a temperature of about 700°C[7-9]. The time allowed for reaction ts between 3 hours[8] and 'This reaction can be performed at temperatures between 550° and 900°C[17,18]. Instead of the carbonate, it is possible to use Li"20[19] or

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“…3). F. Botter (23), reported that LiAlO2 samples showed no measurable change of thermal conductivity after irradiation in OSIRIS to 1% Li burn-up at 600°C, and 2% Li burn-up at 850°C.…”

Section: Transport and Mechanical Properties Thermal Conductivitymentioning

confidence: 99%

Current experimental activities for solid breeder development

Johnson

Hollenberg

Roux

et al. 1989

Fusion Engineering and Design

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I. INTRODUCTION it ,ium containing ceramics are among the principal materials being considered for tritium production 1n future fusion reactors. To ensure a data base adequate for optimization of solid breeder materials, ongoing experimental studies are focused on resolving critical issues related to thermochemical and mechanical behavior, to tritium transport and release, and to material response to a neutron environment. Thermochemical data provide information on tritium solubility and adsorption-desorption characteristics from the ceramic surface. Low solubility is a prerequisite to ensuring low tritium Inventory. Mechanical properties measurements will focus on Young's modulus and elastic stress strain relationships. Neutron Irradiation of candidate materials in closed capsules 1s an approprUV life-test methodology. Both mixed spectrum and hard spectrum Irradiation facilities can be used advantageously. Purge flow 1n-s1tu tritium recovery experiments can be used to test tritium recovery performance of candidate materials. Along with diffusivity data, this Information 1s critical to developing a firm understanding of the ease of tritium recovery. In this paper we will discuss current laboratory and Irradiation experiments for evaluation of candidate breeder materials. Work supported by the U.S. Department of tnergy, Office of l-usion Energy, under contract no. W-31-109-Eng-38.

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Effects of radiation on lithium aluminate samples properties

Cited by 19 publications

References 1 publication

A First-Principles Density Function Theory Study of Tritium Diffusion in Li₂ZrO₃: Application for Producing Tritium

A First-Principles Density Function Theory Study of Tritium Diffusion in Li₂ZrO₃: Application for Producing Tritium

Fabrication, properties, and tritium recovery from solid breeder materials

Current experimental activities for solid breeder development

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Effects of radiation on lithium aluminate samples properties

Cited by 19 publications

References 1 publication

A First-Principles Density Function Theory Study of Tritium Diffusion in Li2ZrO3: Application for Producing Tritium

A First-Principles Density Function Theory Study of Tritium Diffusion in Li2ZrO3: Application for Producing Tritium

Fabrication, properties, and tritium recovery from solid breeder materials

Current experimental activities for solid breeder development

Contact Info

Product

Resources

About

A First-Principles Density Function Theory Study of Tritium Diffusion in Li₂ZrO₃: Application for Producing Tritium

A First-Principles Density Function Theory Study of Tritium Diffusion in Li₂ZrO₃: Application for Producing Tritium