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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

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