1964
DOI: 10.2172/4686227
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Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Abstract: Three Instriimented capsules were irradiated in the MIR to assess the in-reactor performance of the fuel proposed for Core B of the Enrico Fermi Fast Breeder Reactor, Each capsule contained two miniature fuel plates, 2.0 X 0.5 X 0,116 in,, comprised of an 0.102-in.-thick fuel-bearing section containing 33 wt ^ UO2 dispersed in type 347 stainless steel and clad on both surfaces with 0.007-in.-thick type 347 stainless steel. Exposure conditions for the capsules were as follows: Capsule 46-2 46-4 46-5 Sp(ecimen 5

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Cited by 4 publications
(3 citation statements)
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“…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%
“…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%
“…2-11. Additional irradiation results were analyzed in a similar manner by Thurber (1964). The general picture that emerges from these summaries is that moderately loaded UO 2 -SS dispersion fuel can operate successfully to high 235 U burnup at temperatures of up to about 400 °C.…”
Section: Uo 2 In Stainless Steelmentioning
confidence: 99%
“…Figure 6.2 (c) shows a plot of irradiation data for plate-type dispersion fuels circa. 1963 [ 21 ]. Fuels lying to the left of the line are postulated to be stable; those to the right, unstable during irradiation.…”
Section: Dispersion Fuel Particle Conceptsmentioning
confidence: 99%