ORNL-5388 - the Molten Salt Energy Technologies Web Site
ORNL-5388 - the Molten Salt Energy Technologies Web Site
ORNL-5388 - the Molten Salt Energy Technologies Web Site
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4-5%<br />
4.6.2. Carbide- and Metal-Fueled LMFBRS<br />
D. L. Selby<br />
P. M. Haas H. E. Knee<br />
Oak Ridge National Laboratory<br />
Ano<strong>the</strong>r method that is being considered for improving <strong>the</strong> breeding ratios of LMFBRs<br />
and is currently under development1 is one that uses carbide- or metal-based fuels. The<br />
major advantages of <strong>the</strong> metal- and carbide-based fuels are that <strong>the</strong>y will require lower<br />
initial fissile inventories than comparable oxide-based fuels and will result in shorter<br />
doubling times. This is especially true for metal-based fuels, for which doubling times<br />
as low as 6 years have been calculated.2 Since for fast reactors <strong>the</strong> denatured fuel cycle<br />
would have an inherently lower breeding gain than <strong>the</strong> reference plutonium-uranium cycle,<br />
<strong>the</strong>se advantages would be especially important; however, as discussed below, before ei<strong>the</strong>r<br />
carbide- or metal-based fuels can be fully evaluated, many additional studies are needed.<br />
Carbi de-Based Fuels<br />
Carbide-based fuels have been considered for use as advanced fuels in conventional Pu/U<br />
LMFBRs. Burnup levels as high as 120,000 MWD/T appear feasible, and <strong>the</strong> fission gas release<br />
is less than that for mixed oxide fuels.3 Carbide fuels also have a higher <strong>the</strong>rmal conductivity,<br />
which allows higher linear power rates with a lower center-line temperature. In<br />
general, <strong>the</strong> breeding ratio for carbide fuels is higher than <strong>the</strong> breeding ratio for oxide<br />
fuels but lower than that for metal fuels.<br />
Both helium and sodium bonds are being considered for carbide pins. At present 247<br />
carbide pins with both types of bonds are being irradiated in EBR-11. O<strong>the</strong>r differences in<br />
<strong>the</strong> pins include fuel density, cladding type, cladding thickness, type of shroud for <strong>the</strong><br />
sodium-bonded pin, and various power and temperature conditions. The lead pins have already<br />
achieved a burnup level of 10 at.%, and interim examinations have revealed no major problems.<br />
Thus <strong>the</strong>re appears to be no reason why <strong>the</strong> goal of 12 at.% burnup cannot be achieved.<br />
In terms of safety, irradiated carbide fuel releases greater quantities of fission gas<br />
upon melting than does oxide fuel.<br />
ei<strong>the</strong>r an advantage or a disadvantage.<br />
Depending upon <strong>the</strong> accident scenario, this could be<br />
be <strong>the</strong> potential for large-scale <strong>the</strong>rmal interaction between <strong>the</strong> fuel and <strong>the</strong> coolant [see<br />
discussion of potential FCIs (eel-Coolant Interactions) below].<br />
Metal-Based Fuels<br />
Ano<strong>the</strong>r problem associated with carbide fuels may<br />
Reactors with metal-based fuels have been operating in this country since 1951<br />
(Fermi-I, EBR-I, and EBR-11). Relative to oxide- and carbide-fueled systems, <strong>the</strong> metal-<br />
fueled systems are characterized by higher breeding ratios, lower doubling times, higher<br />
heat conductivity, and lower fissile mass. These advantages are somewhat offset, however,<br />
by several disadvantages, including fuel swelling problems that necessitate operation at<br />
lower fuel temperatures.