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ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site

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77<br />

4<br />

will apparently be necessary (see Table .l7Is assuming <strong>the</strong> fuel volume<br />

CfpaRgeS from <strong>the</strong>se additions O<strong>the</strong>r Causes do T3Ot require 3?@lTkOVa% Sf<br />

any fuel to storage, Such additions, which are made over- <strong>the</strong> 30-year<br />

lifetime, would comprise some 38,190 kg (96,332 moles) of UP4 added at<br />

an average of 1,840 kg (3,320 rneles)/year.<br />

~uring operation, 22 many on-stream additions S% fissionable natertal<br />

as molten ~ L ~ were ~ umade P ~ to <strong>the</strong> MSRE, and this method of addition can<br />

obviously be used as a clean, convenient way to add <strong>the</strong> uranium to a DMSW,<br />

Using this method of addition would require use of 2.89 x IO5 moles (7.514<br />

kg) of ?LiF containing 2013 kg of 7Li. This represents about 6.8% of <strong>the</strong><br />

ki in <strong>the</strong> original fuel inventory and would result in appreciable vo~upne<br />

increase (especially if BeF2 were added proportionally) in <strong>the</strong> fuel. t<br />

During <strong>the</strong> course of reactor ope ratio^, removing some fuel tu storage<br />

within <strong>the</strong> reactor complex would probably be necessary if this addition<br />

procedure were used.<br />

Developing and demonstrating methods of addition of solid W4 (or<br />

proper mixtures of UF4 plus UF3) should be possible.<br />

herently more complex (and radioactively dirty), and stating which sf <strong>the</strong><br />

options would be preferred is not presently possible.<br />

These will be in-<br />

Mafntafnfng <strong>the</strong> desired UF3/UF4 ratio. Operation of <strong>the</strong> PlSREl 9s22<br />

demonstrated that in situ production of m3 could be accomplished readily<br />

and conveniently by permitting <strong>the</strong> circulating fuel to react in <strong>the</strong> pump<br />

bowl with a rod of metallic berylPim suspended in a cage of Rastelloy-Ne<br />

This technique could be adapted for use in a DMSR; bery%lim reduction<br />

would be desirable if <strong>the</strong> fissionable and fertile uranium additions are<br />

to be made as 7 ~ 1 ~ ~ 1 7 ~ ~<br />

+<br />

as. Additions would be made as depleted material or as material contain-<br />

ing not more than 28% of 235U in 23*U; <strong>the</strong> materials would be added as<br />

mixed fluorides or possibly as W4 plus LF3.<br />

evelo loping and demonstrating a method of addition of a high-uranium-<br />

content liquid with considerably less LiF than L I ~ U F are ~ almost certddy<br />

goss Bbl e e<br />

'In that event, adding BeF2 will be necessary to preserve <strong>the</strong> LfF/<br />

BeFz ratio in <strong>the</strong> fuel at approximately its initial value.

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