Results of the UNEX process tests with recovery of Cs + Sr and An+REE fractions (flowsheet in Fig. 9.5)

When testing the UNEX process for recovery of the Cs+Sr and An+REE fractions, the following results for recovery of radionuclides were attained: Cs — 99.7%, Sr > 99.98%, Eu > 99.92%. These data permit the bulk HLW being treated to be transferred into the low-level waste (LLW) category, suitable for cementing and subsequent near-surface storage. Barium and lead were almost completely co-extracted with long-lived radionuclides in this process; zirconium and molybdenum were also partly co-extracted. Sodium, potassium iron and mercury remained in the low-level raffinate. In this UNEX process variant, the recovery of HLW components is shown in Table 9.14.

Results of UNEX process tests with the combined recovery of Cs, Sr, An and REE (flowsheet in Fig. 9.6)

When testing the UNEX process, prime attention was given to the work flow which included the combined recovery of Cs, Sr, An and REE into one high-level product to be solidified. It was necessary to reach a degree of

Table 9.14 Content of HLW components in raffinates produced on testing of

UNEX

process with

recovery

of fractions Cs+Sr and An+REE

No

Test

Cs

Sr

Eu

Hg

Zr

Ba

1

0.33%

<0.012%

<0.079%

86.3%

18.6%

<0.43%

2

1.0%

0.023%

<0.074%

89.4%

20.0%

<0.40%

No

Na

K

Fe

Pb

Mo

Test

1

81.4%

60.8%

80.1%

<0.22%

37.4%

2

88.3%

74.8%

84.3%

<0.21%

38.6%

Table 9.15 Distribution of radionuclides in UNEX process flowsheet with combined withdrawal of Cs, Sr, An and REE

Product

137Cs

C/5

О

О)

Alpha

241Am

Raffinate

0.57%

0.0052%

0.040%

0.0002%

Strip agent

100.6%

108.1%

100.4%

105.6%

Scrub solution

0.006%

0.0003%

0.001%

Extractant

0.005%

0.005%

0.02%

0.2%

Material balance

101.1%

108.1%

100.4%

105.8%

Product

238Pu

239Pu

154Eu

99Tc

Raffinate

0.006%

0.002%

0.42%

81.2%

Strip agent

96.9%

103%

78.6%

<0.14

Scrub solution

0.015%

Extractant

0.005%

0.0006%

0.075%

0.013%

Material balance

97.0%

103.9%

79.1%

81.3%

Table 9.16 Distribution of HLW macrocomponents in UNEX process flowsheet with combined withdrawal of Cs, Sr, An and REE

Product

Al Ba

Ca

Fe

Hg

Raffinate

108.2% <1.05%

97.8%

74.7%

110.9%

Strip product

0.14% 105.7%

9.9%

8.3%

<1.2%

Wash

Solvent

0.022% 3.9%

<1.2

0.44%

0.04%

Material balance

108.4% 106.8%

107.7%

83.0%

110.9%

Product

K Mo Na

Nd

Pb

Zr

Raffinate

74.6% 79.1% 108.0%

<2.4%

1.2%

13%

Strip product

27.9% 31.7% 0.13%

112%

83.2%

68.6%

Wash

0.008% — 0.01%

Solvent

0.15% <15,6% 0.02%

<5.5%

<0.62%

0.09%

Material balance

102.4% 110.8% 109.0%

112-114.4%

84.4%

81.6%

radionuclide recovery such that the UNEX-process raffinate conforms to standards established for LLW. The distribution of radionuclides obtained from tests on real HLW in the Idaho National Laboratory is presented in Table 9.15. The distribution of HLW macrocomponents over the workflow products is shown in Table 9.16.

The results of testing show that the recovery rates for Cs, Sr and An are equal to 99.4%, 99.995% and 99.96%, respectively. These recovery rates are sufficient to move the raffinate (the bulk of the wastes being treated) into the LLW category.

The combined stripping of radionuclides was carried out effectively by a solution containing 1 M guanidine carbonate and 20 g/l DTPA. The HLW macrocomponents Ba and Pb were extracted almost completely, whilst Zr, Mo, K, Ca and Fe were only partly extracted (by 87%, 32%, 28%, 10% and 8%, respectively).