05.08.2013 Views

ORNL-4191 - the Molten Salt Energy Technologies Web Site

ORNL-4191 - the Molten Salt Energy Technologies Web Site

ORNL-4191 - 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.

chief indicators of performance. That is, <strong>the</strong><br />

radial peak-to-average power density ratio, which<br />

is about 2.0 for <strong>the</strong> uniform core (which is sur-<br />

rounded, of course, by a heavily absorbing blanket<br />

region and hence behaves essentially as if it were<br />

unreflected), can be reduced to 1.25 or less with<br />

changes in fuel cost and yield of less than 0.02<br />

mill/kwhr (electrical) and 0.2% per year respec-<br />

tively. The enhanced neutron leakage froin <strong>the</strong><br />

core, which results from <strong>the</strong> power flattening, is<br />

taken up by <strong>the</strong> fertile blanket and does not rep-<br />

resent a loss in breeding performance.<br />

Second, attempts at power flattening in two<br />

dimensions have shown that <strong>the</strong> power distribu-<br />

tioil is very sensitive to details of composition<br />

and placement of <strong>the</strong> flattened zone. Small dif-<br />

ferences in upper and lower blanket composition,<br />

which are of no consequence in <strong>the</strong> case of <strong>the</strong><br />

uniform core, produce pronounced axial asymmetry<br />

of <strong>the</strong> power distribution if too much axial flat-<br />

tening is attempted. In addition, <strong>the</strong> axial and<br />

radial buckled zones may interact through <strong>the</strong><br />

flattened zone, to some extent, giving a distri-<br />

bution that is concave upward in one direction<br />

and concave downward in <strong>the</strong> o<strong>the</strong>r, even though<br />

<strong>the</strong> integrated neutron current over <strong>the</strong> entire<br />

boundary of <strong>the</strong> central zone vanishes. In view<br />

of <strong>the</strong>se tendencies, it may be anticipated that a<br />

flattened power distribution would be difficult to<br />

maintain if graphite dimensional changes, result-<br />

ing from exposure to fast neutrons, were allollied<br />

to influence <strong>the</strong> salt volume fractions very strongly<br />

Consequently, some revisions in <strong>the</strong> details of <strong>the</strong><br />

core design are under consideration as a means of<br />

reducing <strong>the</strong> sensitivity of <strong>the</strong> power distribution<br />

to graphite dimensional changes.<br />

Temperature Coefficients ob Reactivity<br />

0. L. Smith C. 0. Thomas<br />

In analyzing power transients in <strong>the</strong> <strong>Molten</strong>-<strong>Salt</strong><br />

Breeder Reactor ... as indeed for most reactors -<br />

one must be able to determine <strong>the</strong> reactivity ef-<br />

fects of temperature changes in <strong>the</strong> individual com-<br />

ponents of <strong>the</strong> core, for example, <strong>the</strong> fuel salt, <strong>the</strong><br />

fertile salt, and <strong>the</strong> graphite moderator. Since <strong>the</strong><br />

fuel is also <strong>the</strong> coolant, and since only small frac-<br />

tions of <strong>the</strong> total heat are generated in <strong>the</strong> fertile<br />

salt and in <strong>the</strong> moderator, one expects very much<br />

smaller temperature changes in <strong>the</strong> latter compo-<br />

88<br />

I<br />

m<br />

0<br />

x<br />

._<br />

-t<br />

a<br />

8<br />

4<br />

I<br />

m<br />

0<br />

x o<br />

t<br />

a<br />

-4<br />

. . . . . . . . . . . . . -<br />

MObERATOR r1<br />

OR N L- DWG 6 7- 1 I8 I2<br />

-8<br />

800 900 1000 800 900 (000<br />

T (OK) r (OK)<br />

Fig. 6.7. MSBR Multiplication Factor vs lemperoture.<br />

nents than in <strong>the</strong> fuel during a power transient.<br />

Expansion of <strong>the</strong> fuel salt, which removes fuel<br />

from <strong>the</strong> active core, is thus expected to be <strong>the</strong><br />

principal inherent mechanism for compensating<br />

any reactivity additions to <strong>the</strong> MSBK.<br />

We have accordingly calculated <strong>the</strong> magnitudes<br />

of <strong>the</strong> temperature coefficients of reactivity sep-<br />

arately for <strong>the</strong> fuel salt, <strong>the</strong> fertile salt, and <strong>the</strong><br />

graphite over <strong>the</strong> range of temperatures from 800<br />

to 1000°K. The results of <strong>the</strong>se calculations are<br />

shown in Fig. 6.7.<br />

In Fig. 6.7a we show a curve of change in mul-<br />

tiplication factor vs moderator temperature (with<br />

6k arbitrarily set equal to zero at 900OK). Similar<br />

curves of Bk vs temperature for fuel and fertile<br />

salts are shown in Figs. 6.7b and 6.7c, and <strong>the</strong><br />

combined effects are shown in Fig. 6.7d. These<br />

curves are all nearly linear, <strong>the</strong> slopes being <strong>the</strong><br />

temperature coefficients of reactivity. The mag-<br />

nitudes of <strong>the</strong> coefficients at 900OK are shown in<br />

Table 6.2.<br />

'The moderator coefficient comes almost entirely<br />

from changes in <strong>the</strong> spectrum-averaged cross sec-

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

Saved successfully!

Ooh no, something went wrong!