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ORNL-4191 - the Molten Salt Energy Technologies Web Site

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6.1 MSBR PHYSICS ANALYSIS<br />

0. L. Smith<br />

Optimization of Reactor Parameters<br />

H. T. Kerr<br />

The two principal indices by which <strong>the</strong> perfor-<br />

mance of <strong>the</strong> <strong>Molten</strong>-<strong>Salt</strong> Breeder Reactor is cus-<br />

tomarily evaluated are <strong>the</strong> cost of power and <strong>the</strong><br />

annual fuel yield, that is, <strong>the</strong> annual fractional in-<br />

crease in <strong>the</strong> inventory of fissionable material.<br />

These are used as figures of merit in assessing <strong>the</strong><br />

influence of various design parameters or <strong>the</strong> effect<br />

of design changes that may be contemplated, and,<br />

in fact, we customarily combine <strong>the</strong>m into a com-<br />

posite figurc of merit,<br />

F = y i lOO(C +~ x>-1 ,<br />

in which 17 is <strong>the</strong> annual fuel yield in percent per<br />

year, C is that part of <strong>the</strong> power cost which de.-<br />

pends on any of <strong>the</strong> parameters considered, and X<br />

is an adjustable constant, having i10 physical sig-<br />

nificance, whose value merely determines <strong>the</strong> rela-<br />

tive sensitivity of F to y and C. Since a large num-<br />

ber of reactor parameters are usually involved, we<br />

make use of an automatic search procedure, carried<br />

out on an IBM 7090 computer, which finds that com-<br />

bination of <strong>the</strong> variable desigu parameters that rnax-<br />

imizes <strong>the</strong> figure of merit, F, subject to whatever<br />

constraints may be imposed by <strong>the</strong> fixed values of<br />

o<strong>the</strong>r design parameters not allowed to vary. This<br />

procedure, called OPTIhfERC, incorporates a mul-<br />

tigroup diffusion calculation (syn<strong>the</strong>sizing a two-<br />

space-dimensional description of <strong>the</strong> flux by al-<br />

ternating one-dimensional flux calculations), a<br />

determination of <strong>the</strong> fissile, fertile, and fission<br />

product concentrations consistent with <strong>the</strong> proc-<br />

A. M Perry<br />

82<br />

essing rates of <strong>the</strong> fuel and fertile salt streams,<br />

and a method of steepest gradients for optiiiiizing<br />

<strong>the</strong> values of <strong>the</strong> variabies. By choosing different<br />

values for <strong>the</strong> constant X in <strong>the</strong> figure of merit, F,<br />

we can generate a curve showing <strong>the</strong> minimum cost<br />

associated with any attainable value of <strong>the</strong> fuel<br />

yield, and by carrying out <strong>the</strong> optimization proce-<br />

dure for different, successive fixed values of se-<br />

lected design parameters, we can generate families<br />

of such curves of C vs y. (In OPTIMEKC any of<br />

some 20 parameters may ei<strong>the</strong>r be assigned fixed<br />

values or be allowed to vary within specified limits<br />

subject to <strong>the</strong> optimization procedure.)<br />

One of <strong>the</strong> design parameters which has a sig-<br />

nificant influence on both yield and power cost is<br />

<strong>the</strong> power density in <strong>the</strong> core. (Actually, <strong>the</strong> core<br />

dimensions for a given total power are <strong>the</strong> param-<br />

eters used.) The performance of <strong>the</strong> reactor is<br />

better at high power densities. At <strong>the</strong> same time,<br />

<strong>the</strong> useful life of <strong>the</strong> graphite moderator, which is<br />

dependent on <strong>the</strong> total exposure to fast neutrons,<br />

is inversely proportional to <strong>the</strong> power density (see<br />

next section). It is necessary, <strong>the</strong>refore, to de-<br />

termine <strong>the</strong> effect of power density on performance<br />

with considerable care.<br />

In Fig. 5.1 <strong>the</strong> fuel-cycle cost is used because<br />

it contains, in fact, most of <strong>the</strong> variation of power<br />

cost with <strong>the</strong> parameters being varied. It may be<br />

seen from Fig. 6.1 that a reduction ii1 power density<br />

from 80 to 20 w/cm3 involves a fuel-cycle cost<br />

penalty of about 0.1 mill/kwhr (electrical) and a<br />

reduction in annual fuel yield of perhaps 1.5%.<br />

,,<br />

Ihere is, of course, also an increase in capital<br />

cost (cf. Chap. 5), but this is essentially offset by<br />

a reduction in <strong>the</strong> cost of replacing <strong>the</strong> graphite<br />

and reactor vessel at intervals determined by radiation<br />

damage to <strong>the</strong> graphite. The combined<br />

penalty for having to replace <strong>the</strong> graphite, compared<br />

with a high-power-density core not requiring<br />

replacement, is about 0.2 mill/kwhr (electrical),

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