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ORNL-4191 - the Molten Salt Energy Technologies Web Site

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Table 6.1. Useful Life of MSBR Graphite<br />

Average Power<br />

Density<br />

(w/crn3!<br />

Life<br />

40 2.0 5. I<br />

40 1.5 7.2<br />

20 2.0 10.8<br />

20 1.5 14.4<br />

as well as on <strong>the</strong> total dose. The dose rate in <strong>the</strong><br />

DFR was approximately ten times greater than that<br />

expected in <strong>the</strong> MSBR, and if <strong>the</strong>re is a significant<br />

dose-rate effect, <strong>the</strong> life of <strong>the</strong> graphite in an MSBR<br />

might be ra<strong>the</strong>r longer than shown in Table 6.1.<br />

Flux Flattening<br />

0. L. Smith H. T. Kerr<br />

Eecause <strong>the</strong> useful life of <strong>the</strong> graphite moderator<br />

in <strong>the</strong> MSBR depends on <strong>the</strong> maximum value of <strong>the</strong><br />

damage flux rattier than on its average value in <strong>the</strong><br />

core, <strong>the</strong>re is obviously an incentive to reduce <strong>the</strong><br />

maximum-to-average flux ratio as much as possible,<br />

provided that this can be accomplished without se-<br />

rious penalty to o<strong>the</strong>r aspects of <strong>the</strong> reactor per-<br />

formance. In addition, <strong>the</strong>re is an iilcentive to<br />

make <strong>the</strong> temperature rise in parallel fuel passages<br />

through <strong>the</strong> core as nearly uniform as possible, or<br />

at least to minimize <strong>the</strong> maximum deviation of fuel<br />

outlet temperature from <strong>the</strong> average value. Since<br />

<strong>the</strong> damage flux (in effect, <strong>the</strong> total neutron flux<br />

above 50 kev) is essentially proportional to <strong>the</strong><br />

fission density per unit of core volume, <strong>the</strong> first<br />

incentive requires an attempt to flatten <strong>the</strong> power<br />

density per unit core volume throughout <strong>the</strong> core,<br />

that is, in both radia.1 and axial directions in a<br />

cylindrical core. Since <strong>the</strong> fuel moves through <strong>the</strong><br />

core only in <strong>the</strong> axial direction, <strong>the</strong> second in-<br />

centive requires an attempt to flatten, in <strong>the</strong> radial<br />

direction, <strong>the</strong> power density per unit volume of<br />

fuel. Both objectives can be accomplished by<br />

maintaining a uniform volume fraction of fuel salt<br />

throughout <strong>the</strong> core and by flattening <strong>the</strong> power<br />

density distribution in both directions to <strong>the</strong><br />

greatest extent possible.<br />

87<br />

The general approach taken to flattening <strong>the</strong><br />

power distribution is <strong>the</strong> classical one of pro-<br />

-,<br />

viding a central core zone with I

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