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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Fig. 4.12. Time Dependence of Samarium Poisoning and Approximate Control Rod Reactivity During <strong>the</strong> First<br />
Period of Operation of MSRE with 233U Fuel Loading.<br />
and 23R1J burnup effects.) The resultant curve in<br />
Fig. 4.12 indicates that regulating rod insertion<br />
will be required for about <strong>the</strong> first 79 days of<br />
operation.<br />
Because <strong>the</strong> samarium acts as a burnable poison,<br />
<strong>the</strong> amount of excess uranium required for operation<br />
will be largely governed by <strong>the</strong> requirements for<br />
calibration of <strong>the</strong> control rods. There should he<br />
considerable latitude in this choice, determined in<br />
part by criteria of control rod sensitivity at <strong>the</strong><br />
operating point and by <strong>the</strong> maximum time OC opera-.<br />
tion desired before refueling.<br />
4.4 MSRE DYNAMICS WITH 233u FUEL<br />
S. J. Ball<br />
The dynamic behavior of <strong>the</strong> NKRE has been<br />
analyzed for <strong>the</strong> case of 2,"3U-bearing fuel salt by<br />
using <strong>the</strong> MSHE frequency response (:ode MSFR.<br />
The only differences in input data for <strong>the</strong> 233U<br />
and <strong>the</strong> reference 23sU calculations are in those<br />
parameters compared in Table 4.5. The most im-<br />
port.ant difference is <strong>the</strong> lower delayed-neutron<br />
fraction for <strong>the</strong> 233U1 which makes <strong>the</strong> neutron<br />
level mote responsive to changes in reactivity.<br />
For a given fast change in rod reactivity, <strong>the</strong><br />
immediate flux response would be two to three<br />
times greater with 233U than with 235U. ?'his<br />
effect will probably require a minor modification in<br />
'OS. J. Ball arid T. W. Krrlin, Stability Arinfysis of thr<br />
<strong>Molten</strong> <strong>Salt</strong> React3r Experiment, ORNl,-TR.I-1070 (Decem-<br />
ber 19665).<br />
<strong>the</strong> present MSRE rod control system tu compensate<br />
for <strong>the</strong> higher system gain.<br />
The predicted effect of 233U on <strong>the</strong> MSKE inherent<br />
stability, as indicated by <strong>the</strong> phase margin,<br />
and <strong>the</strong> natural period of oscillation are shown as<br />
a function of power level in Fig. 4.13. The phase<br />
margin l1 is a typical measure of system stability,<br />
<strong>the</strong> smallet phase margins indicating reduced stability.<br />
A general rule of thumb in control practice<br />
is that a phase margin of at least 30" is desirable;<br />
phase margins of 20" or less indicate lightly<br />
damped oscillations and thus poor control. Hence<br />
<strong>the</strong> predicted inherent stability for <strong>the</strong> "U system<br />
is greater than for 2 3 5 for ~ a11 power levels.<br />
The faster response oE <strong>the</strong> 233W system, as indicated<br />
by <strong>the</strong> smaller natural periods of oscillation,<br />
is due to <strong>the</strong> higher gain of <strong>the</strong> neutron kinetics.<br />
Experimentally determined values of period of<br />
oscillation for <strong>the</strong> 23sU system ate also shown in<br />
Fig. 4.13 for comparison. ' Although direct<br />
measurements of phase margin were not made, <strong>the</strong><br />
stability chatacteristics as indicated by frequency<br />
response measurements were also in good agreement<br />
with <strong>the</strong> predictions.<br />
It is concluded that no serious operational difficulties<br />
are to be expected due to <strong>the</strong> differences in<br />
dynamic hehavior resulting from <strong>the</strong> 233U fuel<br />
loading.<br />
"J. E. Gibson, Nonlinear Automatic ContrOf, chap. 1,<br />
McGraw-Hill, New York, 1963.<br />
"T. W. Karlin and S. J. Bell, Experimentaf Dynamic<br />
Arialysis of <strong>the</strong> <strong>Molten</strong> <strong>Salt</strong> Reactor Experiment, ORNrd-<br />
TM-1647 (October 196b)-