TABLE 8.B.1 UREX+ Processes

Process

Product 1

Product 2

Product 3

Product 4

Product 5

Product 6

Product 7

UREX+1

U

Tc

Cs and Sr

TRU and lanthanide fission products

Other fission products

 

 

UREX+1a

U

Tc

Cs and Sr

TRU

Other fission products (including lanthanides)

 

 

UREX+2

U

Tc

Cs and Sr

Pu and Np

Am, Cm, and lanthanide fission products

Other fission products

 

UREX+3

U

Tc

Cs and Sr

Pu and Np

Am and Cm

Other fission products (including lanthanides)

 

UREX+4

U

Tc

Cs and Sr

Pu and Np

Am

Cm

Other fission products

Note: Am = americium; Cm = curium; Cs = cesium; Np = neptunium; Pu = plutonium; Sr = strontium; Tc = technetium; TRU = transuranic elements; U = uranium.

Source: Idaho National Laboratory, August 10, 2006. Available at www-fp.mcs.anl.gov/nprcsafc/Presentations/NucPhysConf.pdf; accessed May 12, 2009.

separation is also considered to be in the proof-of-principle stage of development, and commercial-scale deployment of this technology is unlikely before 2035.19

Thorium Fuel Cycles

In addition to the fuel cycles described above, closed fuel cycles using thorium (an element approximately three times more abundant in nature than uranium) are possible. The use of thorium-based fuel cycles has been studied for about 30 years, but on a much smaller scale than for uranium or uranium/plutonium cycles (see

19

Electrochemical separation has been used on a small scale for the Experimental Breeder Reactor-II (EBR-II) fuel and blanket at Argonne National Laboratory.



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