I reckon they will go for option B2 somehow?
"the recovered U is re-enriched to 3–5% 235 U, if necessary, and fabricated into UO2 fuel for recycle back into an LWR. Alternatively, the U could go directly to fuel fabrication for a fast reactor"
Maybe they could even make HALEU out of the recovered U for some SMR's that are coming.
Also worth noting is the the Natrium is a fast reactor? whadayareckon!
7.2.2 Developing Electrochemical Sensors
Real-time quantification of the chemical species within fuel processing streams is essential for proper process control and nuclear material accountancy. Electroanalytical sensors offer a variety of approaches for achieving these measurements in aqueous, pyroprocessing, and molten salt–relevant applications.
Electroanalytical sensors use the electrochemical response of electrodes immersed into the process solution to determine the chemical composition and redox state of the fluid. This electrochemical response can range from passive measurements (e.g., certain potentiometric approaches) to active signals applied to the electrodes (e.g., voltammetry). The concentration of species in the fluid is ultimately related to the sensor response using electroanalytical formulas or correlation curves.
Figure B.2 presents an example fuel cycle scenario with multirecycle of U and Pu. Again, fresh U oxide fuel is burned in an LWR in this scenario. But in this case, the used fuel from the LWR is processed to recover the bulk U and a mixed U/Pu product.
Eliminating the separation of pure Pu is desirable from the standpoint of nuclear nonproliferation. These separations could be achieved through the Co-Extraction (COEX™
(Drain et al. 2008), Advanced PUREX (Fox et al. 2006), or co-decontamination (Lumetta et al.
2019) processes. As in the example in Figure B.1,
the recovered U is re-enriched to 3–5% 235 U, if necessary, and fabricated into UO2 fuel for recycle back into an LWR. Alternatively, the U could go directly to fuel fabrication for a fast reactor. The mixed U/Pu is fabricated into fast reactor fuel. Eventually, the U and Pu are continually separated and recycled into the fast reactor. All HLW generated during the actinide separation processes is immobilized and disposed of in a geological repository
https://www.ornl.gov/file/innovativ...evelopment-needs-advanced-fuel-cycles/display
View attachment 5369272
View attachment 5369275
View attachment 5369293
(20min delay)