ORNL-4191 - the Molten Salt Energy Technologies Web Site
ORNL-4191 - the Molten Salt Energy Technologies Web Site
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