05.08.2013 Views

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

SHOW MORE
SHOW LESS

Create successful ePaper yourself

Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.

3-3.3.3 Fuel maintenance ol3tions and methods<br />

The initial fuel charge for a INSR can be prepared in a high state<br />

of purity and introduced into <strong>the</strong> reactor by minor variamts of <strong>the</strong><br />

methods* used for <strong>the</strong> MSRE4 and proposed for <strong>the</strong> MSBR.8 For a once-<br />

through BMSR that proposes no chemical repr~cessing to remove fission<br />

products, <strong>the</strong> required fuel maintenance olperati~ns are relatively fewe<br />

They include (1) continu~t~s removal (by <strong>the</strong> sparging and stripping sec-<br />

tion of <strong>the</strong> reactor) of fission-product krypton and xenon, (2) addition<br />

of 2 3 5 ~ and '3% to replace that lost by burnup and to keep <strong>the</strong> fuel suf-<br />

ficiently denatured, and (3) in situ pr~du~tion of UF3 to keep <strong>the</strong> redox<br />

potential of <strong>the</strong> fuel at <strong>the</strong> desired level; <strong>the</strong>y probably also include<br />

(4) removal of inadvertent oxide contaminants from <strong>the</strong> fuel; in addition,<br />

<strong>the</strong>y may include (5) addition of "4 to replace that lost by tranmuta-<br />

tion or stored with fuel removed from <strong>the</strong> operating circuit and (6) re-<br />

moval 05 a portion of <strong>the</strong> insol~bke noble and seminoble fission products.<br />

Each of <strong>the</strong>se is discussed briefly in <strong>the</strong> following sections.<br />

Continuous removal of fission-product krypton and XC~OEB. Stripping<br />

of krypton and xenon makes possible <strong>the</strong>ir continuous removal from <strong>the</strong> re-<br />

actor circuit by <strong>the</strong> purely physical means of stripping with helium. For<br />

<strong>the</strong> reference-design MSBR,* helim flowing at 0.005 m3/s (10 cfm) was to<br />

be injected continuously into and withdram from fuel-salt side streams<br />

carrying a total of 0.35 m'/s or about 10% of <strong>the</strong> total fuel flow rate,<br />

generally similar operation should prove optimal for <strong>the</strong> DMSR. Such<br />

a stripping circuit would remove an appreciable (but not a major) fraction<br />

of <strong>the</strong> tritium and a small (perhaps very small) fraction of <strong>the</strong> noble and<br />

seminoble fissiom products as gas-bor~ne particulates. In addition, <strong>the</strong><br />

stripper would remove BF3 if leaks sf secodary coolant iRtO <strong>the</strong> fuel<br />

were to occur.<br />

None of <strong>the</strong>se removals (except possibly <strong>the</strong> last) appre-<br />

ciably affect <strong>the</strong> chemical behavior of <strong>the</strong> fuel system.<br />

Addition sf fissionable and fertile uranium. Adding -4,470 kg of<br />

"'u and -18,400 kg of 23% during <strong>the</strong> lifetime of <strong>the</strong> once-through DNSR<br />

*<br />

FWI for <strong>the</strong> MSRE was prepared in relatively small ~atches.22s85<br />

If DKSRs were to be of commercia% consequence, continuous purification<br />

systems would certainly be devised for initial fuel preparation.

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!