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Management of Commercially Generated Radioactive Waste - U.S. ...

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K.29<br />

TABLE K.3.4 Retention Time Ranges on 1-m Barriers for<br />

Several Radionuclides (Neretnieks 1977)<br />

Retention Time, Years<br />

10% Bentonite/<br />

Radionuclide 90% Quartz Clinoptilolite<br />

90Sr 30 600 to 1,400<br />

137 Cs 20 to 30 2,200 to 5,200<br />

226Ra 40 to 50 600 to 1,400<br />

229 Th 50 to 300 unknown<br />

237Np 2.1 x 106 unknown<br />

239Pu 2.4 x 104 unknown<br />

241Am 458 1,000 to 30,000<br />

9 Tc 1 1<br />

1291 1 1<br />

TABLE K.3.5 Barrier Depth (m) Required to Retard Various<br />

Radionuclides 30 Half-Lives (Neretnieks 1977)<br />

30 Half-Lives Barrier Depth, m<br />

10% Bentonite/<br />

Radionuclide 90% Quartz Clinoptilolite<br />

Sr 1 0.2<br />

Cs 1 0.1<br />

2 26 Ra 40 1.5<br />

241Am 1 0.1 to 0.7<br />

If the reduced or oxidized species is less soluble than the original radionuclide solu-<br />

tion species, an oxidation-reduction (redox) reaction may be used to retard the mobilities<br />

<strong>of</strong> certain radionuclides. Very little work has been done using redox controlling materials<br />

as migration retardants. An example <strong>of</strong> redox control is the use <strong>of</strong> wustite (FeO) to surround<br />

the waste form. The oxidation <strong>of</strong> ferrous to ferric ion would reduce technetium in the<br />

highly mobile pertechnetate ion (TcO 4 ) from Tc(VII) to Tc(IV). (Latimer 1952 and Pourbaix<br />

1966). Tc(IV) is a much less mobile form <strong>of</strong> technetium than Tc(VII).

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