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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$ .p9 3.3.3.1 Preparation of initial fuel<br />
problems.<br />
Initial purification procedures for <strong>the</strong> DNSR present no formidable<br />
Nuclear poisoms (e.g., boron, cadmium, or lanthanides) are not<br />
common contaminants of <strong>the</strong> constituent raw materials. All <strong>the</strong> pertinent<br />
cmpsunds contain at least small amounts of water, and all are readily<br />
hyarsliyzea to oxides ana oxyfluorides at elevated temperatures. he COW-<br />
pounds LiF and BeF2 generally contain a small quantity of sulfur as SUI-<br />
fate ion. Uranium tetrafluoride commonly contains small amonts of U0zp<br />
UFg, and U82F2.<br />
purification prseeaures63 ,*4 %85 uses to prepare materials for <strong>the</strong><br />
aircraft reactor experiment (ARE), <strong>the</strong> MSRE, and many laboratory and en-<br />
gineering experiments have treated <strong>the</strong> mixed materials at. high tempera-<br />
ture (usually at 600°C) with gaseous H~-HP mixtures and <strong>the</strong>n with pure H2<br />
in equipment of nickel or copper. me HF-HZ treatment serves to (1) re-<br />
duce <strong>the</strong> 6T5* and U6+ to u4+, (2) reduce SU%fat@ ts sulfide and BI€3SlOVe it<br />
as H~S, (3) remove CP- as HCP, and ( 4) ~snvert <strong>the</strong> oxides and oxyfluorides<br />
to fluorides. Final treatment with H2 serves to reduce PeF3 and FeF2 to<br />
insoluble iron and to remove NiF2 that may have been produced during hy-<br />
drofluorination, To date, all preparations have been performed in batch<br />
equipment but eontiwuous equipment has been partially developed. 86 8 87<br />
For a DMSR, as for <strong>the</strong> MSRE,*% purificatfsn of <strong>the</strong> bulk of <strong>the</strong> fuel<br />
would presumably be conducted on L~F-B~F~-T~FL+-UP~ mixtures containing<br />
perhaps 85 to 90% sf <strong>the</strong> required WL, and on molten Li3UF7 to provide <strong>the</strong><br />
additional uranium necessary to bring <strong>the</strong> fuel to <strong>the</strong> critical and oper-<br />
ating Concentration.<br />
Such a purification procedure can provide a sufficiently pure and<br />
eompletely homogeneous fuel material for initial operation of <strong>the</strong> reactor.<br />
3.3.3.2 Contamination possibilities<br />
Though <strong>the</strong> fuel material can be supplied and introduced into <strong>the</strong><br />
reactor in sufficiently pure fom, contamination of <strong>the</strong> fuel is possible<br />
ESOre SeQePal SOUlllC@S e<br />
O<strong>the</strong>r reactor materials. a%e moderator graphite can contain a large<br />
quantity of 602, C6, and H28 by virtue of its porosity and internal