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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5-22<br />
In <strong>the</strong> case of metal-clad oxide fuels that are thorium based, <strong>the</strong> areas requiring<br />
fur<strong>the</strong>r study are essentially <strong>the</strong> same as those listed above for <strong>the</strong> Pu/U oxide fuels; how-<br />
ever, in contrast to Pu/U-oxide fuels, where significant effort has already been devoted<br />
toward resolving this list 0; areas, relatively little R&D has been performed to date for<br />
thorium-based fuels and consequently a larger amount of research and development would be<br />
required.<br />
The intense radioactivity of <strong>the</strong> decay daughters of 232U (which is produced in <strong>the</strong><br />
thorium along with <strong>the</strong> 233U) requires that <strong>the</strong> refabrication processes all be remotely<br />
operated and maintained. This requirement will necessitate additional development of <strong>the</strong><br />
refabrication processes and may require <strong>the</strong> development of new fabrication methods.<br />
qualification of U/Th and Pu/Th oxide fuels will also require additional R&D efforts.<br />
fuel element.<br />
HTGR fuels are coated uranium oxide or carbide microspheres embedded in a graphite<br />
have been identified; however, additional R&D prior to construction of a hot demonstra-<br />
tion facility is needed.<br />
The process and equipment concepts for refabricating HTGR fuel remotely<br />
This should cover:<br />
(1) <strong>the</strong> scaleup of refabrication equipment,<br />
(2)<br />
(3)<br />
(4)<br />
<strong>the</strong> recycle of scrap material,<br />
<strong>the</strong> control of effluents, and<br />
<strong>the</strong> assay of fuel-containing materials.<br />
Additional R&D will also be required for qualification of <strong>the</strong> recycle fuel.<br />
While <strong>the</strong> reference HTGR fuel cycle already includes thorium, fur<strong>the</strong>r development work<br />
will be required to fabricate DUTH fuels for HTGRs because of <strong>the</strong> requirement of a higher<br />
uranium content of <strong>the</strong> fiss<br />
irradiation.<br />
Fuel Reprocessing<br />
le part<br />
The<br />
cle and <strong>the</strong> increased production of plutonium during<br />
The basic technology for reprocessing of uranium and uranium/plutonium oxide pellet<br />
fuels with low burnup exists in <strong>the</strong> Purex process.<br />
of government reprocessing experience with military-related fuels;<br />
This technology is based on many years<br />
reprocessing plant for mixed oxide power reactor fuels that conforms to current U.S. federal<br />
and state requirements has not yet been operated.<br />
pilot-scale work has been successfully carried out on ‘all important processes and components<br />
of <strong>the</strong> reprocessing plant, operability, reliability, and costs of an integrated plant have<br />
not been demonstrated in all cases at fuel exposures expected in commercial reactors.<br />
Specific areas that still require development work include <strong>the</strong> following:<br />
however, a commercial<br />
Additionally, while engineering or<br />
(1 ) operation and maintenance of <strong>the</strong> mechanical headend equipment;<br />
(2) ‘methods for handling highly radioactive residues that remain after <strong>the</strong> dissolution<br />
(3)<br />
of high-burnup fuel;<br />
<strong>the</strong> technology for reducing radioactive off-gas releases (e.g., Kr-85, iodine and<br />
tritium) to conform to anticipated regulations;