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
You also want an ePaper? Increase the reach of your titles
YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.
6-41<br />
-<br />
L<br />
L<br />
L<br />
-<br />
i<br />
e<br />
6.2.6 Converter-Breeder System with Light Plutonium "Transmutation"<br />
The results presented in <strong>the</strong> preceding sections have demonstrated that nuclear<br />
power systems based on converter reactors will ultimately be limited by <strong>the</strong> quantity of<br />
economically recoverable uranium.<br />
While a larger U308 resource base will allow larger<br />
systems to develop, <strong>the</strong> converse is also true. Since <strong>the</strong> U308 resource base has always<br />
been somewhat uncertain, <strong>the</strong> deployment of fast breeder reactors has traditionally been<br />
considered as <strong>the</strong> method by which <strong>the</strong> consequences of this uncertainty would be minimized.<br />
Thus, it has historically been assumed that by deploying'FBRs nuclear power systems would<br />
outgrow <strong>the</strong> constraints naturally imposed by <strong>the</strong> U308 resource base.<br />
In <strong>the</strong> option discussed here (Option 6), an FBR with a plutonium-uranium core and a<br />
thorium blanket is located in <strong>the</strong> energy center to produce 233U which is <strong>the</strong>n used in de-<br />
natured converter reactors outside <strong>the</strong> center.<br />
rate could be obtained with a plutonium-thorium core in <strong>the</strong> FBR, this option is referred<br />
to as having a Zight "Pu-~o-~~~U" transmutation rate.<br />
contained in this option are shown in Fig. 6.1-4.<br />
Because a higher plutonium "transmutation"<br />
The individual reactor concepts<br />
The nuclear contribution associated with this option when all <strong>the</strong> converters utilized<br />
are LWRs (Case 6L) is shown in Fig. 6.2-29. In this case, even with <strong>the</strong> high-cost U308<br />
supply, <strong>the</strong> system is capable of maintaining a net addition rate of 15 GWe/yr throughout<br />
<strong>the</strong> planning horizon - i.e., from 1980 through 2050. The ability of <strong>the</strong> nuclear system<br />
to maintain this net addition rate is a direct consequence of <strong>the</strong> compound system doubling<br />
time of <strong>the</strong> FBR, which, in this case, is 13 yr. This doubling time in turn is a direct<br />
consequence of <strong>the</strong> FBR having a Pu-U core.<br />
In this option <strong>the</strong> installed nuclear capacity which must be located in energy centers<br />
increases as a function of time to approximately 560 GWe in year 2050 (see Fig. 6.2-30).<br />
The most rapid increase occurs between 2010 and 2020 as <strong>the</strong> number of FBRs on line in-<br />
creases significantly. The amount of nuclear capacity available for installation outside<br />
<strong>the</strong> centers increases from approximately 300 GWe in year 2000 to over 500 GWe in year 2050.<br />
Initially, <strong>the</strong> LWR loaded with approximately 3% enriched 235U is <strong>the</strong> principal reactor<br />
available, but as <strong>the</strong> U308 is depleted, it is replaced by <strong>the</strong> LWR loaded with 11% 233U<br />
in 238U. This is illustrated in Fig. 6.2-31, which also indicates that this option is<br />
capable of maintaining an energy support ratio greater than unity throughout <strong>the</strong> planning<br />
horizon.<br />
The maximum annual U308 and enrichment requirements for this case are 62,000 !jT/yr<br />
and 44 million SWUlyr, respectively. These annual requirements do not differ significantly<br />
from those obtained with <strong>the</strong> LWR on <strong>the</strong> throwaway cycle, <strong>the</strong> reason being that in ei<strong>the</strong>r<br />
case, <strong>the</strong> goal of <strong>the</strong> nuclear power system is to maintain a net addition rate of 15 GWe/yr<br />
provided this increase can be sustained by <strong>the</strong> U308 supply.<br />
The maximum installed capacity