Preparation and evaluation of fission product retaining fuel for the III A charge of the Pluto Loop. Part I. Preparation of fuel. Project DRAGON

Technical Report · Sun Sep 15 04:00:00 EDT 1963

OSTI ID:4115330

Gough, J. R.C.; Burnett, R. C.; Beutler, H.; Redding, G. B.

The requirements were for enriched uranium dicarbide particles coated with pyrolytic carbon and consolidated into fuel cartridges of total length 36 in. The required fuel loading was 28.7 g of U-235 uniformly distributed throughout 18 fuel cartridges, each of nominal length 2 in. and nominal diameter 1.75 in. Fig. 1 shows the design of the fuel cartridge adopted for this irradiation. The six longitudinal channels at the outer circumference carry the fission product purge flow between the cartridge and the inner surface of the fuel tube. The chamber at one end obviates the need to align the grooves during assembly, while the central 5 in. diameter hole facilitates uniform deposition of carbon during the gas cracking operation. In addition to the fuel cartridges, 8 "satellite" fuel compacts were supplied for bum-up determinations. Each satellite fuel compact of diameter 0.3 in. and length 0.2 in. contained 0.0046 g of U-235; this represented a similar fuel density to that of the fuel cartridges.

• Research Organization: Atomic Energy Establishment (AEE), Winfrith, England (United Kingdom)
• NSA Number: NSA-24-040992
• OSTI ID: 4115330
• Report Number(s): DP-Report--214(Pt.1)
• Country of Publication: United Kingdom
• Language: English

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COATED FUEL PARTICLES
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