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
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REACTIVITY<br />
POWER<br />
<strong>ORNL</strong>- DWG 67- 9191<br />
-<br />
16 18 20 22 24 26 28 3C 1 3 S 7 9<br />
JULY, 1967 nus, 1967<br />
residual reactivity occurred during <strong>the</strong> first<br />
several weeks of run 11. Detailed analysis of <strong>the</strong><br />
individual terms revealed two sources of error.<br />
One was a gradual downward drift in <strong>the</strong> temperature<br />
indicated by two of <strong>the</strong> four <strong>the</strong>rmocouples<br />
used to calculate <strong>the</strong> average reactor outlet temperature.<br />
These two <strong>the</strong>rmocouples were eliminated<br />
and replaced by one o<strong>the</strong>r that had not<br />
drifted. The second error was caused by loss of<br />
significance in <strong>the</strong> calculation of <strong>the</strong> 14'Sm concentration.<br />
In <strong>the</strong> program, only <strong>the</strong> change in<br />
samarium concentration is computed, and that<br />
change is added to <strong>the</strong> last value to obtain <strong>the</strong><br />
current value. As <strong>the</strong> I4'Sm concentration approached<br />
85% of its equilibrium value, <strong>the</strong> incremental<br />
concentration change computed for <strong>the</strong> 5-<br />
miri time step between routine reactivity balances<br />
was outside <strong>the</strong> five-decimal-digit precision of <strong>the</strong><br />
computer. As a result, <strong>the</strong>se increinents were<br />
lost when <strong>the</strong> concentration was updated. To<br />
avoid using doubl e-precision arithmetic, <strong>the</strong> program<br />
was modified to only update <strong>the</strong> 14'Srn and<br />
<strong>the</strong> 'Sm concentrations every 4 hr while <strong>the</strong><br />
reactor is at steady po~~i. Summary calculations<br />
made off line were used to verify <strong>the</strong> adequacy<br />
of this change.<br />
Fig. 1.6. Residual Reactivity During MSRE Run 12.<br />
When <strong>the</strong>se corrections were introduced on<br />
March 1'7, <strong>the</strong> apparent downward drift in reactivity<br />
disappeared. At <strong>the</strong> same time, minor<br />
changes were made in some of <strong>the</strong> '35Xe stripping<br />
parameters to make <strong>the</strong> calculated steady-state<br />
xenon poisoning agree more closely with <strong>the</strong> observed<br />
value.<br />
O<strong>the</strong>r small reactivity variations were observed<br />
in run 11, for example, from March 29 to April 9.<br />
These changes are directly related to changes in<br />
<strong>the</strong> helium overpressure on <strong>the</strong> fuel loop; a 1-psi<br />
pressure increase leads to a reversible reactivity<br />
decrease of slightly less than 0.01% 6k/k. The<br />
mechanism through which pressure and reactivity<br />
are coupled has not yet been established. The<br />
direct reactivity effect of <strong>the</strong> change in circulating<br />
voids caused by a change in absolute pressure<br />
is at least a factor of 10 smaller than <strong>the</strong> observed<br />
effect of pressure on reactivity. The time constant<br />
of <strong>the</strong> pressure-reactivity effect is relatively<br />
long, suggesting a possible connection through <strong>the</strong><br />
xenon poisoning.<br />
Fuel additions were made for <strong>the</strong> first time in<br />
run 11 with <strong>the</strong> reactor at full power. Nine capsules<br />
containing a total of 761 g of 235U were<br />
added between April 18 and 21. The reactivity-