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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)-

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