HIGH-TEMPERATURE IRRADIATION TEST OF UO$sub 2$ CERMET FUELS

Keller, D.L.; Cunningham, G.W.; Murr, W.E.; Fromm, E.; Lozier, D.E.

doi:10.2172/4711314

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Dispersion Fuel3

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“…Figure 6.7 shows a postirradiation image of a dispersion of UO 2 particles in a niobium matrix. [ 38 ]. The fuel loading in this case is 80 percent by volume.…”

Section: Alternate Dispersion Fuel Conceptmentioning

confidence: 97%

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Gas-Cooled Fast Reactor (GFR) FY04 Annual Report

Weaver¹,

Totemeier²,

Clark³

et al. 2004

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“…Figure 6.7 shows a postirradiation image of a dispersion of UO 2 particles in a niobium matrix. [ 38 ]. The fuel loading in this case is 80 percent by volume.…”

Section: Alternate Dispersion Fuel Conceptmentioning

confidence: 97%

“…Dispersions using this concept have been proven to work well in combination with ductile matrices such as steel [ 19 ] and niobium [ 20 ]. Figure 6.2 (a) shows a schematic drawing of this fuel type.…”

Section: Dispersion Fuel Particle Conceptsmentioning

confidence: 99%

Gas-Cooled Fast Reactor (GFR) FY04 Annual Report

Weaver¹,

Totemeier²,

Clark³

et al. 2004

View full text Add to dashboard Cite

“…Such particles typically include a distribution of approximately 15% open porosity to act as a fission gas 'plenum' reducing the gas-driven pressure on the matrix. Dispersions using this concept have been proven to work well in combination with ductile matrices such as steel [10] and niobium [11]; performance has been postulated to be limited by a combination of fission density and temperature [12]. Analysis of GFR fuel requirements, however, eliminates metal alloys from consideration (see below).…”

Section: Dispersion Fuelmentioning

confidence: 99%