ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site
ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site
ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site
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6<br />
2. I Fuel Circuit<br />
The fuel circuit for a DNSR would be very similar to that for an<br />
f.1SBR; only <strong>the</strong> core design would be changed. The primary requirement<br />
for this redesign<br />
density) to<br />
a realaction in <strong>the</strong> core neutron faux (ana power<br />
1. extend <strong>the</strong> life expectancy of <strong>the</strong> graphite moderator to <strong>the</strong> full 30-<br />
2.<br />
year plant %ifetLaae,<br />
limit neutron captures in 233~a which, to enhance pro~~feration re-<br />
sistance, would be retained in <strong>the</strong> fuel salt.<br />
me lower power density would also tend to reduce <strong>the</strong> poisoning effects<br />
of short-lived fission products and to simplify <strong>the</strong> <strong>the</strong>rmal-hydraulic con-<br />
straints on <strong>the</strong> design of <strong>the</strong> moderator elements, The principal unfavor-<br />
able effects would be <strong>the</strong> increases in inventory of <strong>the</strong> fuel salt and fis-<br />
sile fuel. Reference-design features of <strong>the</strong> DNSR core are described in<br />
greater detail in a later section.<br />
At design power (h000 MWe), <strong>the</strong> fuel salt, which would have a liqui-<br />
*<br />
dug temperature of about 5OO"c, would enter <strong>the</strong> core at 566"~ and leave<br />
at 704'C to transport about 2250 PlWt (in four parallel loops) to <strong>the</strong> sec-<br />
ondary salt, The flow rate of salt in each ~f <strong>the</strong> primary loops (includ-<br />
ing <strong>the</strong> bypass for xenon stripping) be a ~ ~ I u&/s t (a6,o00 gpm>.<br />
IFfme primary salt would ~~ntain 0.5 to 1% (by volume) helium bubbles to<br />
serve as a strip ing agent for xenon and o<strong>the</strong>r volatile fission products,<br />
Helim WQUI~ be added to and removed from bypass flows of -10% of each<br />
of <strong>the</strong> primary hoop flowse This gas stripping would also remove some of<br />
<strong>the</strong> tritium from <strong>the</strong> primary salt,t partly as ~HF; p~owever, nost of <strong>the</strong><br />
tritium would diffuse through <strong>the</strong> tube walls of <strong>the</strong> primary heat exchang-<br />
ers into <strong>the</strong> secondary salt. Helium reraoved from <strong>the</strong> primary circuit<br />
would be treated in a series of fission-product trapping and cleanup steps<br />
before being recycled for fur<strong>the</strong>r gas stripping. P~-ovisions would alls~ be<br />
cooling 0<br />
* %he temperature at which <strong>the</strong> first crystals appear on equilibrium<br />
P~stimates are that 18 to 19% 0% <strong>the</strong> total tritiw produced wml~l<br />
removed in this gas,<br />
be