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Table 3.3-3. Enriched Proauct Compositions
(Weight Fraction in Uranium)
Isotope
Fuel Type B
Feed Product
Fuel Type c
Feed Product
2321) 5.02 x lom4 4.1545 x 10-3 6.565 x loe4 5.626 x
233u 0.11861 1 0.90 0.11498 0.90
2341) 0.008523 0.03757 0.0351 08
0.0901
2351) 0.00231 7 0.00376 0.01255 0.00379
23611 3.6 10-5 1.98 10-5 0.005327 1.73 10-4
2381) 0.87001 1 0.05450 0.831 228 3.124 x lo-'+
2s3U in Tails 0.01 0.01
Feed Flow, 832
kg U/yr
Product F1 ow, 100
kg U/yr
When removed from the plant, the UF, product would be condensed and probably stored in
monel cylinders.
gamma dose rates that could be expected from the unshielded cylinders are as shown in
Table 3.3-5. To reduce these product dose rates to acceptable levels would require substan-
tial shielding. As an example, Table 3.3-6 shows the shielding required to reduce the dose
rate at 1 ft to 1.0 and 50 mr/hr.
If it is assumed that the cylinders were sized to hold 16 kg of UF6, the
859
Table 3.3-4. Gamma Radiation Level in an Enrichment Plant
as a Function of 232U Concentration
Tjzu Concentration Radiation Level (r/hr)
(wt X )
at Equi 'I i bri urn*
2.0 6.8
1 .o 3.4
0.5 1.7
0.1 .34
100
0.001 .0034
0.0001 .00034
* Within an infinite array of centrifuges.
bi