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ORNL-5388 - the Molten Salt Energy Technologies Web Site

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3-8<br />

The values in Table 3.1-2 are a result of a standard HTGR fuel composition which<br />

has an average Th/233U ratio of about 20. Preliminary estimates have been made of dena-<br />

tured HTGR fuels which assume a 20% denatured 235U, leading to a 15% denatured 233U.6<br />

Because of <strong>the</strong> added 2381) fertile material, <strong>the</strong> amount of thorium is correspondingly re-<br />

duced by about 30%, resulting in a similar reduction in <strong>the</strong> 232U production. The con-<br />

centration of 232U in total uranium would also be reduced by <strong>the</strong> mere presence of <strong>the</strong><br />

diluting 238U, so that it can be estimated that a 15% denatured 233U HTGR would contain<br />

approximately 40 ppm 232U in uranium after equilibrium recycle. The lower 232U levels<br />

in <strong>the</strong> HTGR are primarily due to a softening of <strong>the</strong> neutron energy spectrum compared with<br />

that of <strong>the</strong> LWR. This results in a marked reduction in <strong>the</strong> 232Th(n,2n') reaction rate,<br />

which is a prime source of 232U.<br />

3.1.3. Fast Breeder Reactor Fuels<br />

232U concentrations calculated by Mann and Schenter' and by Burns8 for various<br />

Except for Case 2, tnese<br />

conunercial-sized FBR fuel cycles are given in Table 3.1-3.<br />

values were determined from reacti on-rate cal cul ati ons using 42 energy groups and one-<br />

dimensional geometry; <strong>the</strong> Case 2 results were determined from a coarse nine-group two-<br />

dimensional depletion calculation.<br />

It is important to note that Cases 1 and 2 represent <strong>the</strong> "transmuter" concept. All<br />

<strong>the</strong> discharged uranium (23211, 233U, 2s4U, and 235U) is bred from <strong>the</strong> 232Th initially<br />

charged and consists principally of 2331).<br />

will be reduced by a factor of 5 to 8 in <strong>the</strong> denatured fuel manufactured from this mate-<br />

rial.<br />

approximately 150-750 ppm 23211 in uranium.<br />

This accounts for <strong>the</strong> high 232U/U ratio, which<br />

Thus, denatured fuel generated via <strong>the</strong> fast Pu/Th transmuter is expected to have<br />

Case<br />

NO. Fuel<br />

Table 3.1-3. FBR Core Region 232U Discharge Concentrations'<br />

2321) in u (PP~)<br />

t=lyrb t = 2 y r t = 3 y r t = 5 y r<br />

No recycle<br />

1 10% 239Pu in Th 982 1710 2380 3270<br />

2 11% 239Pu i n Th 1106 2376 3670<br />

3 10% 233U in Th 288 830 1330 221 0<br />

4 10% 2331) in 238U 6.6 10.7 12.5 13.3<br />

With recycle<br />

5 10% 233U in Th 1820 2760 3260<br />

6 10% 23311 in 23% 35 35 35<br />

aCases 1, 3-6 are from ref. 7; Case 2 is from ref. 8.<br />

bt = fuel residence time for no recycle cases; t = burning time before recycle for<br />

recycle cases.<br />

L<br />

L<br />

L<br />

II<br />

I!<br />

Ll

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