UO2 properties affecting performance

Lyons, M.F.; Boyle, R.F.; Davies, Julie; Hazel, V.E.; Rowland, T.C.

doi:10.1016/0029-5493(72)90072-6

Cited by 41 publications

(15 citation statements)

References 23 publications

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“…Their results showed a thermal conductivity of $17 W/m/K at 200°C and $11 W/m/K at 1000°C. This is much higher than the thermal conductivity of a UO 2 pellet, which is 6 W/m/K at 200°C and $3 W/m/ K at 1000°C [26]. The higher thermal conductivity of the SiC IMF pellet will reduce the temperature gradient across the pellet during operation.…”

Section: Estimated In Reactor Behavior Of the Fabricated Sic Imf Pelletmentioning

confidence: 97%

“…The formation of these bubbles causes fuel swelling. ''If the fission gas is released before the bubbles can grow, there obviously will be less gaseous swelling in the fuel'' [26]. The open pores of the SiC IMF pellet in this study can potentially work as a pathway for the fission gas to diffuse out of the fuel and solve the fuel swelling problem.…”

Section: Estimated In Reactor Behavior Of the Fabricated Sic Imf Pelletmentioning

confidence: 98%

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Low-temperature synthesis of silicon carbide inert matrix fuel through a polymer precursor route

Shih

Tulenko

Baney

2011

Journal of Nuclear Materials

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Section: Estimated In Reactor Behavior Of the Fabricated Sic Imf Pelletmentioning

confidence: 97%

Section: Estimated In Reactor Behavior Of the Fabricated Sic Imf Pelletmentioning

confidence: 98%

Low-temperature synthesis of silicon carbide inert matrix fuel through a polymer precursor route

Shih

Tulenko

Baney

2011

Journal of Nuclear Materials

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“…When the population of off-stoichiometric clusters grow in the matrix, the matrix itself becomes off-stoichiometric even if the overall material is stoichiometric. Indeed, several studies confirmed the tendency of UO 2 , for example, to oxidize, i.e., become hyper-stoichiometric by irradiation, which implies that defect clustering proceeds in a non-stoichiometric fashion (Hassan et al, 2013;Lyons et al, 1972;Gupta, 2015). Offstoichiometry consideration in defect clustering is thus critical for the interpretation of experimental observations of irradiated oxides.…”

Section: Introductionmentioning

confidence: 95%

Off-stoichiometric defect clustering in irradiated oxides

2017

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A cluster dynamics model describing the formation of vacancy and interstitial clusters in irradiated oxides has been developed. The model, which tracks the composition of the oxide matrix and the defect clusters, was applied to the early stage formation of voids and dislocation loops in UO 2 , and the effects of irradiation temperature and dose rate on the evolution of their densities and composition was investigated. The results show that Frenkel defects dominate the nucleation process in irradiated UO 2. The results also show that oxygen vacancies drive vacancy clustering while the migration energy of uranium vacancies is a rate-limiting factor for the nucleation and growth of voids. In a stoichiometric UO 2 under irradiation, off-stoichiometric vacancy clusters exist with a higher concentration of hyperstoichiometric clusters. Similarly, off-stoichiometric interstitial clusters form with a higher concentration of hyperstoichiometric clusters. The UO 2 matrix was found to be hyper-stoichiometric due to the accumulation of uranium vacancies.

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“…UO 2 synthesis and fabrication has been described and we only summarize the main aspects here. Oxide fuel fabrication for light water reactors (LWR) begins with the process of enrichment.…”

Section: Current 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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UO2 properties affecting performance

Cited by 41 publications

References 23 publications

Low-temperature synthesis of silicon carbide inert matrix fuel through a polymer precursor route

Low-temperature synthesis of silicon carbide inert matrix fuel through a polymer precursor route

Off-stoichiometric defect clustering in irradiated oxides

Opportunities for Advanced Ceramics and Composites in the Nuclear Sector

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