Fabrication development of Li2O pebbles by wet process

Tsuchiya, Kazuyoshi; Fuchinoue, Katsuhiro; Saito, Shozaburo; Watarumi, K.; Furuya, Takemi; Kawamura, Hiroshi

doi:10.1016/s0022-3115(97)00312-7

Cited by 11 publications

(6 citation statements)

References 8 publications

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“…The relative density of the Li 2 O ceramic spheres sintered at 900°C, 1000°C, and 1100°C was 79.66% TD, 81.51% TD, and 82.54% TD, respectively. Notably, the Li 2 O spheres prepared by this advanced granulation method can achieve a crush load of 40 N and a theoretical density of nearly 80% TD after sintering at 900°C, which was not achievable by the methods reported in the previous literature 16‐18 …”

Section: Resultsmentioning

confidence: 92%

“…To date, there are three types of lithium compounds used as raw materials for the preparation of Li 2 O sintered pebbles, namely lithium carbonate (Li 2 CO 3 ), lithium peroxide (Li 2 O 2 ), and lithium hydroxide (LiOH). The researchers prepared these lithium compounds into millimeter‐sized spherical particles by sol‐gel method, wet method or melting method, and then heated to a high temperature to decompose lithium compounds into Li 2 O 16‐18 . However, the decomposition of lithium compounds into lithium oxide is very slow.…”

Section: Introductionmentioning

confidence: 99%

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Highly efficient preparation of Li₂O breeder materials with core‐shell structure by oil‐based granulation route

Chen

Shi

et al. 2020

J Am Ceram Soc

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This paper gives an oil‐based granulation approach to realize the efficient preparation of Li2O breeder materials, which solve the problems of long preparation cycle, high manufacturing cost and difficult to be homogenization and densification in the past. Li2O precursor spheres with narrow size distribution and uniform spherical shape can be obtained using paraffin oil as binders. The Li2O feed powder with bimodal size distribution will self‐organize to form a core‐shell structured sphere during granulation, in which the core and shell are composed of small particles and large particles, respectively. Notably, the Li2O ceramic spheres sintered at 900°C can achieve a crush load of 40.69 ± 4.01 N and a theoretical density of 79.66% TD, which was not achievable by the methods reported in the previous literature. The strategy proposed in this work not only can be easily extended to other material systems but also opens up a new avenue for the design and preparation of tritium breeder materials with uniform size distribution and satisfactory mechanical properties.

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Section: Resultsmentioning

confidence: 92%

Section: Introductionmentioning

confidence: 99%

Highly efficient preparation of Li₂O breeder materials with core‐shell structure by oil‐based granulation route

Chen

Shi

et al. 2020

J Am Ceram Soc

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“…The ceramic breeders will likely be in the form of small pebbles; these giving reduced thermal stress and ensuring a better fit inside complex blanket geometries. Li 2 O pebbles can be fabricated using a wet or sol‐gel process . Li 2 TiO 3 can also be produced using a wet process or by performing extrusion‐spheroidization‐sintering (see Fig.…”

Section: Future Nuclear Applications Of Ceramicsmentioning

confidence: 99%

Opportunities for Advanced Ceramics and Composites in the Nuclear Sector

et al. 2013

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Ceramics have played a crucial role in the development of fission based nuclear power, in glass & glass composite high level wasteforms, in composite cements to encapsulate intermediate level wastes (ILW) and also for oxide nuclear fuels based on UO2 and PuO2/UO2 mixed oxides. They are also used as porous filters with the ability to absorb radionuclides (RN) from air and liquids and are playing a key role in the cleanup at Fukushima. Non‐oxides also find current fission applications including in graphite moderators and B4C control rods. Ceramics will continue to be significant in the near‐term expansion of nuclear power via next‐step developments of fuels with inert matrices or based on thoria and in wasteforms using alternative composite cements or single or multiphase ceramics that can host Pu & other difficult RN. Longer term advances for Generation IV reactors, which will operate at higher temperatures & with higher fuel burn‐up require innovative fuel developments potentially via carbides & nitrides or composite fuel systems. Novel non‐thermal (cement‐like) and thermal techniques are currently being developed to treat some of the difficult legacy wastes. Non‐thermally derived wasteforms developed from geopolymers, composite cements, hydroceramics, and phosphate‐bonded ceramics and thermally derived wasteforms made by Hot Isostatic Pressing and fluidized bed steam reforming (FBSR) as well as vitrification techniques based on cold crucible melting (CCM), Joule‐heater in‐container melting and plasma melting (PM) are described. Future developments in waste treatment will be based on separation technologies for partitioning individual RN along with design & construction of RN‐containing ceramic targets for inducing transmutation reactions. Near demonstration actinide‐hosting ceramic wasteforms including multiphase Synroc systems are described. Opportunities also exist for ceramics in structural applications in Generation IV reactors such as composite SiC/SiC and C/C for fuel cladding and control rods and MAX phases and ultrahigh‐temperature ceramics (UHTCs) may find near core fuel coating and cladding applications. Uses of ceramics in fusion reactor systems will be both functional (ceramic superconductors in magnet systems for plasma control and in Li silicate breeder blankets in tokamaks) and structural including as sapphire diagnostic windows, graphite diverters, and plasma facing C and UHTCs. In all these cases, performance is limited by poorly understood radiation damage and interface controlled processes, which demands a combined modeling/experimental approach.

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“…A meltincjdropping process was used by JAERI in collaboration with Mitsubishi to produce 1 mm Li20 spheres [3]. b) Sol-gel type processes are being investigated at JAERI, with NFI Ltd., to produce 1 mm Li20 [4,5] and 1.5 mm Li2Ti03 pebbles [4,6]. After sintering, densities in the range of 80-85% TD were obtained for both materials [4,6].…”

Section: Preparation and Fabrication Of Ceramic Breedersmentioning

confidence: 99%

“…b) Sol-gel type processes are being investigated at JAERI, with NFI Ltd., to produce 1 mm Li20 [4,5] and 1.5 mm Li2Ti03 pebbles [4,6]. After sintering, densities in the range of 80-85% TD were obtained for both materials [4,6]. In addition, these processes are attractive as effective use of resources and reduction of radioactive wastes [7].…”

Section: Preparation and Fabrication Of Ceramic Breedersmentioning

confidence: 99%

Ceramic breeder materials: Status and needs

Johnson

Noda

Roux

1998

Journal of Nuclear Materials

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Fabrication development of Li2O pebbles by wet process

Cited by 11 publications

References 8 publications

Highly efficient preparation of Li₂O breeder materials with core‐shell structure by oil‐based granulation route

Highly efficient preparation of Li₂O breeder materials with core‐shell structure by oil‐based granulation route

Opportunities for Advanced Ceramics and Composites in the Nuclear Sector

Ceramic breeder materials: Status and needs

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Fabrication development of Li2O pebbles by wet process

Cited by 11 publications

References 8 publications

Highly efficient preparation of Li2O breeder materials with core‐shell structure by oil‐based granulation route

Highly efficient preparation of Li2O breeder materials with core‐shell structure by oil‐based granulation route

Opportunities for Advanced Ceramics and Composites in the Nuclear Sector

Ceramic breeder materials: Status and needs

Contact Info

Product

Resources

About

Highly efficient preparation of Li₂O breeder materials with core‐shell structure by oil‐based granulation route

Highly efficient preparation of Li₂O breeder materials with core‐shell structure by oil‐based granulation route