26.08.2015   Advanced separation techniques for nuclear fuel reprocessing and radioactive waste treatment

UREX+1a

The process was demonstrated in 2005 and 2006 and yielded high recovery of all products. Excellent TRU/Ln recovery was obtained with TRUEX, and a refined TALSPEAK process for the 2006 test met target specifications. The CCD-PEG separations module was not run as part of the 2005 dem­onstration. Results are given in Table 7.3.

UREX+2

The process was demonstrated in 2004 and yielded high recovery of all products. All primary components reported to their desired product streams.

Table 7.3 UREX+1a demonstration results. Percent distribution of process effluents

Year

2005

2006

Component

Product

Other effluents

Product

Other effluents

UREX

U

>99.98

<0.02

99.997

0.003

Tc

97.1

2.9

95.5

4.5

CCD-PEG

Cs

NA

NA

>99.85

<0.15

Sr

NA

NA

99.1

0.1

TALSPEAK

Pu

99.8

0.2

>99.995

<0.005

Am

99.999

0.001

>99.97

<0.03

Ln

12

88

<0.03

>99.97

NA: Not applicable.

Table 7.4 UREX+2 demonstration results. Percent distribution of process effluents

Component

Product

Raffinate

2004 Co-extraction U

>99.9994

0.003

Tc

80.1

18.6

Pu

99.8

0.2

Np

2004 CCD-PEG

87.2

12.8

Cs

99.7

0.3

Sr

>98.6

<1.4

The Tc and Np fractions found in the streams in which they were targeted were lower than the target values. Zirconium reported to the Np/Pu product, rather than the raffinate, due to other-phase carryover that was ascribed to a mismatch between the contactor design and loaded-solvent density. Results are given in Table 7.4.