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

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

56<br />

to bring that understanding to <strong>the</strong> level that exists for LiP-BeF2 solu-<br />

tions.<br />

Oxide-fluoride behavior. The behavior of molten flu~ridie systems<br />

such as <strong>the</strong> DMSB fuel mixture can be affected markedly by addition of<br />

significant concentrations sf oxide ispa, For example, we know that crys-<br />

tals of UO2 precipitate when welts of EiF2-UF4 are treated with a reac-<br />

tfve oxide such as water v a ~ o r ~ ~ 9 ~ ~ ~ 9 3 3<br />

The solubilities of <strong>the</strong> actinide dioxides in L~F-B~F~-T~F~-.UFL+ mix-<br />

tures are low, and <strong>the</strong>y decrease in <strong>the</strong> order Tho2, Pa02, U0z9 and<br />

~~02.29 16-24<br />

oreo over^ <strong>the</strong>se dioxides all psssess <strong>the</strong> same (fluorite)<br />

crystal structure and can all form solid solutions with one ano<strong>the</strong>r.<br />

Sokmbility products and <strong>the</strong>ir temperature dependence have been mea-<br />

sured; 34-43 <strong>the</strong>ir behavior is generally we11 understood.<br />

Trivalent plutonium shows little or no tendency to precipitate as<br />

oxide from LiF-BeF2-ThPq-UFq mixtures 27<br />

bility seems to be general for trivalent oxides, it is highly lfkeky<br />

that precipitation of h203 and o<strong>the</strong>r trivalent actinides would be dif-<br />

ficult to achieve.<br />

Because relatively large so%u-<br />

If Pa4+ is oxfdized to Pa5+ (which can be do~e readily in LiF-BeF2-<br />

ThF4-UF4 by treatment with anhydrous and hydrogen-free KF gas), <strong>the</strong>n Pa205<br />

(QP an addition compound of it> can be precipitated selectively.4l3 44<br />

such oxidation to pas* can be avoided by maintaining a small fraction of<br />

<strong>the</strong> uranium as UF3 in <strong>the</strong> fuel mixture.<br />

he relaiively ~ s oxide w tolerance of DMSR fuel will require reason-<br />

able care to avoid inadvertent precipitation of actinide oxides within <strong>the</strong><br />

reactor system.<br />

substantially diluted with ii2> serves to Lower <strong>the</strong> oxide concentration<br />

to tolerable levels. 18,45<br />

However, treatment of melts with anhydrous I-iF (even when<br />

Compatibility of fuel with reactor materials, <strong>Molten</strong> fluorides are<br />

excellent fluxes for many materials. Though some oxides are relatively<br />

insokuble, most are readily dissolved, and d l are rapidly recrystal-<br />

lized; consequently, protective coatings are n ~ useful, t and <strong>the</strong> bare<br />

clean metal must withstand C Q P ~ Q S ~ attack. V ~ The reactor metal (Hastel-<br />

loy-N, described Prt detail in Sect, 3.4) was chosen and tailored to be<br />

<strong>the</strong>gm~dp~i~ieally stable to <strong>the</strong> fuel components, as much as possible,<br />

_.<br />

. . . . . .. ., .<br />

w

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

Saved successfully!

Ooh no, something went wrong!