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ORNL-5388 - the Molten Salt Energy Technologies Web Site

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7-29<br />

7.4. ADEQUACY OF NUCLEAR POWER SYSTEMS UTILIZING DENATURED 233U FUEL<br />

FOR MEETING ELECTRICAL POWER DEMANDS<br />

M. R. Shay, D. R. Haffner, W. E. Black, T. M. Helm,<br />

R. W. Hardie, and R. P. Omberg<br />

Hanford Engineering Development Laboratory<br />

An important measure for evaluating a nuclear power system is whe<strong>the</strong>r it can meet<br />

projected power demands with <strong>the</strong> uranium resources estimated to be available at an accept-<br />

able cost.<br />

This section summarizes <strong>the</strong> results of analyses performed in this study to<br />

determine whe<strong>the</strong>r various nuclear power systems uti1 izing denatured 233U fuel could meet<br />

a projected power demand of 350 GWe installed capacity by <strong>the</strong> year 2000 and a net increase<br />

of 15 GWe/year through <strong>the</strong> year 2049, <strong>the</strong> total capacity in <strong>the</strong> year 2050 being 1100 GWe.<br />

The analyses were based on a uranium supply model shown in Fig. 7.4-1 and in Table B-7<br />

(Appendix B) , which provides both conservative and optimistic predictions of <strong>the</strong> uranium<br />

supply as a function of cost.<br />

The power systems analyzed are described in detail in Chapter 6. They are comprised<br />

of LEU-LWRs operating in conjunction with LWRs on o<strong>the</strong>r fuel cycles or in conjunction with<br />

one of <strong>the</strong> three types of advanced converters (SSCR, HWR, or HTGR) considered in <strong>the</strong> study.<br />

In some cases, FBRs are included in <strong>the</strong> system.<br />

resistant power systems was one of <strong>the</strong> primary concerns, <strong>the</strong> concept of a secure energy<br />

<strong>ORNL</strong>-DWG 78-24717<br />

Since <strong>the</strong> maintenance of proliferation-<br />

center supporting dispersed reactors was<br />

used, with <strong>the</strong> fuel utilized in <strong>the</strong> dis-<br />

persed reactors restricted to LEU (or SEU)<br />

260 I I I I I I I I I I and denatured fuels. A reactor operating on<br />

240 -<br />

-<br />

-<br />

<strong>the</strong> denatured 233U fuel cycle is not self-<br />

sustaining, however, and <strong>the</strong>refore it<br />

200 - requires an exogenous source of 23%. In<br />

-In- -<br />

<strong>the</strong> power systems studied, <strong>the</strong> 233U is<br />

provided by MEU/Th-fueled <strong>the</strong>rmal reactors<br />

or pl utoni um-fuel ed <strong>the</strong>rmal and/or fast<br />

- transmuters. These reactors, of course,<br />

a1 so contribute to <strong>the</strong> power generation.<br />

Because <strong>the</strong> transmuters have plutonium cores ,<br />

however, <strong>the</strong>y must be located within <strong>the</strong> secure<br />

-<br />

-<br />

-<br />

-<br />

-<br />

energy centers. (Note: With this restriction<br />

<strong>the</strong> "energy support ratio'' of a nuclear<br />

system becomes a second important measure<br />

1 1 1 1 ' " - of evaluation, as is discussed in Section<br />

0 .<br />

0<br />

1<br />

t<br />

'<br />

2 ' 3 4 5 6 7 8 9 + O t !<br />

u30e OUANTITY (to6 tons)<br />

Fig. 7.4-1. Marginal Costs for High-<br />

and Intermediate-Cost U308 Supply Curves.<br />

7.2.3. The energy support ratios for <strong>the</strong><br />

systems described here are given in Appendix<br />

C, along with o<strong>the</strong>r detailed results from<br />

<strong>the</strong> analyses. )

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