Carbide Fuel

Sengupta, Arijit; Agarwal, Renu; Kamath, H.S.

doi:10.1016/b978-0-08-056033-5.00051-3

Cited by 13 publications

(11 citation statements)

References 49 publications

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“…As they react easily with oxygen and moisture, all processing of the materials was carried out in nitrogen-filled glove boxes with moisture and oxygen levels below 50 ppm each. These operating conditions are less severe than those practiced in India where the carbide fuel fabrication facility consists of chains of interconnected gloves boxes with moisture and oxygen levels below 25 ppm each [1]. But, even these levels are too high to avoid some oxygen pickup, particularly when handling finely milled carbides.…”

Section: Carbide Fabricationmentioning

confidence: 94%

“…So, the higher the Pu content, the higher the allowable oxygen content. Hence, for Indian fuels with a plutonium content ranging from 55 to 70% [1], an oxygen content up to 6000 ppm is specified.…”

Section: Mixed Carbide Pellet Requirementsmentioning

confidence: 99%

“…Their high metal atom density (12.9 g cm −3 vs 9.8 g cm −3 ) and their high thermal conductivity (about eight times higher than the oxide one), the latter compensating for their lower melting point (Table 1), are among the advantages of mixed carbide fuels over the widely used oxide fuels for current nuclear power generation [1]. Moreover, their compatibility with the coolant allows them to be safely used in liquid metal (Na) or gas cooled (He) reactors.…”

Section: Introductionmentioning

confidence: 99%

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Fabrication of mixed uranium–plutonium carbide fuel pellets with a low oxygen content and an open-pore microstructure

Duguay

Pelloquin

2015

Journal of the European Ceramic Society

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Section: Carbide Fabricationmentioning

confidence: 94%

Section: Mixed Carbide Pellet Requirementsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Fabrication of mixed uranium–plutonium carbide fuel pellets with a low oxygen content and an open-pore microstructure

Duguay

Pelloquin

2015

Journal of the European Ceramic Society

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“…Recent developments of nonoxide nuclear fuels have been reviewed for carbides by Sengupta et al . and for nitrides by Arai .…”

Section: Future Nuclear Applications Of Ceramicsmentioning

confidence: 99%

“…Carbide fuels have been used in test reactors in for example the USA (EBR‐II), Russia (BOR60), Japan (JFR 2), and France (RAPSODIE). The Indian FBR program started with Pu‐rich mixed U,Pu carbide as the driver fuel in its loop‐type fast breeder test reactor which went critical in 1985 and remains the only reactor operating on a full core of carbide fuel . Ternary nonoxide systems for example (U,Pu) oxycarbides and UO 2 /UC 2 mixtures are being examined in the F‐BRIDGE EC Project: basic research for innovative fuel design for GEN IV systems …”

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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