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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3-35<br />
3.3.5. Deterrence .Value of 232U Contamination in Denatured Fuel<br />
C. M. Newstead<br />
Brookhaven National Laboratory<br />
The preceding sections have emphasized that unless 232U i s isotopically separated<br />
from 233U, both it and its daughter products will always exist as a contaminant of <strong>the</strong><br />
fissile fuel. And since as 232U decays to stable 208Pb i<strong>the</strong> daughter products emit several<br />
high-intensity gamma rays (see Fig. 3.0-l), all 23% fuel, except that which has undergone<br />
recent purification, will be highly radioactive. While <strong>the</strong> gama rays, and to a lesser<br />
extent <strong>the</strong> decay alpha and beta particles and <strong>the</strong> neutrons from a,n reactions, will intro-<br />
duce complications into <strong>the</strong> fuel cycle, <strong>the</strong>y will ais0 serve as a deterrent to <strong>the</strong> seizure<br />
of <strong>the</strong> fuel and its subsequent use in <strong>the</strong> fabrication of a clandestine nuclear explosive.<br />
Consider, for example, <strong>the</strong> steps that would have to be followed in producing and using such<br />
a device:<br />
1. Diverting or seizing <strong>the</strong> fissile material (as reactor fuel elements or as bulk<br />
material).<br />
2. a. Chemically reprocessing <strong>the</strong> spent fuel to separate out <strong>the</strong> bred fissile plu-<br />
tonium (or 233Pa) or<br />
b. Isotopically enriching <strong>the</strong> fresh fuel or bulk material to increase <strong>the</strong> 233U con-<br />
centration in uranium sufficiently for its use in a weapon.<br />
3. Fabricating <strong>the</strong> fissile material into a configuration suitable for an explosive<br />
device.<br />
4. Arming and delivering <strong>the</strong> device.<br />
As indicated, at Step 2 a decision must be made as to which fissile material is to be<br />
employed, 239Pu o r 233U.<br />
require a chemical separation capability analogous to that required for current LEU spent<br />
fuel; however, <strong>the</strong> quantity of spent denatured fuel (i.e., kilograms of heavy metal) that<br />
would have to be processed to obtain a sufficient amount of 239Pu would be increased by a<br />
factor of 2 to 3 over <strong>the</strong> amount of LEU fuel that would have to be processed.<br />
for some reactor systems, <strong>the</strong> quaZity (i,e., <strong>the</strong> fraction of <strong>the</strong> material which is fissile)<br />
of <strong>the</strong> plutonium recovered from denatured fuel would be somewhat degraded relative to <strong>the</strong><br />
LEU cycle.<br />
Extracting <strong>the</strong> plutonium present in spent denatured fuel would<br />
Moreover,<br />
The selection of 233U as <strong>the</strong> weapons fissile material means, of course, that <strong>the</strong><br />
material being processed through all <strong>the</strong> operations listed above would be radioactive. While<br />
both national and subnational groups would be inhibited to some degree by <strong>the</strong> radiation<br />
field, it is clear that a national group would be more likely to have <strong>the</strong> resources and<br />
technological base necessary to overcome <strong>the</strong> radiation hazard via remote hand1 ing, shielding,<br />
and various cleanup techniques.<br />
Thus, <strong>the</strong> radiation field due to <strong>the</strong> 232U contamination<br />
would be effective in limiting proliferation by a nation to <strong>the</strong> extent that it would com-<br />
plicate <strong>the</strong> procedures which <strong>the</strong> nation would have to follow in employing this path and