ORNL-5388 - the Molten Salt Energy Technologies Web Site
ORNL-5388 - the Molten Salt Energy Technologies Web Site
ORNL-5388 - the Molten Salt Energy Technologies Web Site
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4-50<br />
where RF is <strong>the</strong> reprocessing recovery factor (0.98). While such an expression i s not<br />
absolutely correct, it does provide a measure of <strong>the</strong> relative growth capability of each<br />
reactor. Since <strong>the</strong> data sumnarized in Table 4.5-1 are based on three separate reference<br />
LMFBRs operating with a variety of design differences and fuel management schemes, <strong>the</strong><br />
above expression was used simply to provide relative values for each system. It should<br />
also be noted that sane reactor configurations listed have dissimilar core and axial<br />
blanket materials and thus would probably require modifications to standard reprocessing<br />
procedures.<br />
The data presented in Table 4.5-1, although preliminary, do serve to indicate cer-<br />
tain generic characteristics regarding <strong>the</strong> impact of <strong>the</strong> alternate LMFOR fuel options.<br />
considering those cases in which similar core materials but different blanket materials<br />
By<br />
are utilized it is clear that <strong>the</strong> choice of <strong>the</strong> blanket material has only a ra<strong>the</strong>r small<br />
effect on <strong>the</strong> reactor physics parameters. On <strong>the</strong> o<strong>the</strong>r hand, <strong>the</strong> impact of changes in <strong>the</strong><br />
core fissile and fertile materials is considerable, particularly on <strong>the</strong> breeding ratio.<br />
Utilizing 233U as <strong>the</strong> fissile material results in a significant decrease in <strong>the</strong> breeding<br />
ratio relative to <strong>the</strong> corresponding Pu-fueled case (ranging from 0.10 to 0.15, depending<br />
on <strong>the</strong> system). This decrease is due primarily to <strong>the</strong> lower value of v (neutrons produced<br />
per fission) of 2% relative to 239Pu and 241Pu. Somewhat compensating for <strong>the</strong> difference<br />
in v is <strong>the</strong> fact that <strong>the</strong> capture-to-fission ratio of 233U is significantly less than that<br />
of <strong>the</strong> two plutonium isotopes. The differences in breeding ratios given in Table 4.5-1<br />
reflect <strong>the</strong> net result of <strong>the</strong>se two effects, <strong>the</strong> decrease in v clearly dominating. Use of<br />
233U as <strong>the</strong> fissile material also results in a slight decrease in <strong>the</strong> fissile inventory<br />
required for criticality. This is due to two effects, <strong>the</strong> lower capture-to-fission ratio<br />
of 233U relative to <strong>the</strong> plutonium isotopes, and <strong>the</strong> obvious decrease in <strong>the</strong> atomic weight<br />
of 233U relative to Pu (% 2.5%).<br />
. The replacement of 2j*U by zs2Th as <strong>the</strong> core fertile material also has a significant<br />
impact on <strong>the</strong> overall breeding ratio regardless of <strong>the</strong> fissile material utilized. As <strong>the</strong><br />
data in Table 4.5-1 indicate, <strong>the</strong>re is a substantial breeding ratio penalty associated<br />
with <strong>the</strong> use of 232Th as a core material in an LMFBR. This penalty is due to <strong>the</strong> much<br />
lower fast fission effect in 232Th relative to that in 2s*li (roughly a factor of 4 lower).<br />
The fertile fast fission effect is reflected in <strong>the</strong> breeding ratio in two ways. First,<br />
although <strong>the</strong> excess neutrons generated by <strong>the</strong> fission of a fertile nucleus can be sub-<br />
sequently captured by fertile material. <strong>the</strong>ir production is not at <strong>the</strong> expense of a<br />
fissile nucleus. Moreover, <strong>the</strong> fertile fission effect produces energy, <strong>the</strong>reby reducing<br />
<strong>the</strong> fission rate required of <strong>the</strong> fissile material to maintain a given power level. Since<br />
both <strong>the</strong>se effects act to improve <strong>the</strong> breeding ratio, it is not surprising that use of<br />
Th-based fuels result in significant degradation in <strong>the</strong> breeding ratio. A fur<strong>the</strong>r<br />
consequence of <strong>the</strong> reduced fast fission effect of 232Th is a marked increase in fissile<br />
inventory required for criticality, evident from <strong>the</strong> values given in Table 4.5-1 for <strong>the</strong><br />
required initial loadings.<br />
a<br />
> 3<br />
3<br />
3<br />
3<br />
3<br />
a<br />
1<br />
3<br />
3<br />
3<br />
1<br />
3<br />
1<br />
3