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RD&D-Programme 2004 - SKB

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Influence of hydrogen on dissolution of alpha-doped uranium dioxide<br />

Since radical-rich gamma and beta radiation have a favourable effect on hydrogen activation<br />

accompanied by consumption of radiolytic oxidants, the relevance of the results for the scenario<br />

with spent fuel in a repository can rightfully be questioned. Since virtually only alpha radiation<br />

is expected to persist for a long time, the favourable effect of gamma and beta radiation would<br />

diminish progressively. A material that resembles old fuel is alpha-doped uranium dioxide,<br />

where different quantities of an alpha-emitting isotope are homogeneously distributed in the<br />

uranium dioxide matrix. Alpha-doped uranium oxide has been synthesized in cooperation<br />

with ITU in Karlsruhe. As a part of <strong>SKB</strong>’s work in the EU project SFS, leaching of a uranium<br />

dioxide pellet doped with ten percent uranium-233 was studied in a titanium autoclave under<br />

three different hydrogen pressures. Leaching was started with a 10 mM sodium chloride solution<br />

under a hydrogen pressure of 16 bar. Samples of the solution were taken at different times<br />

and analyzed by alpha spectrometry. After four months, the estimated uranium concentration<br />

in the solution was still less than 3·10 –10 M. To dissolve all oxidized uranium from the pellet,<br />

a bicarbonate solution was added to the autoclave, but no changes were noted in the uranium<br />

concentration. No measurable dissolution of uranium could be observed, not even when the<br />

hydrogen pressure was reduced to 1.6 bar during a 178-day period. The hydrogen pressure was<br />

further reduced by a factor of ten to 0.16 bar (1.6 bar of argon with a hydrogen concentration of<br />

6.08 percent by volume) during a 141-day period. Preliminary results from alpha radiometric<br />

analyses of uranium-233 are shown in Figure 15-6.<br />

The results show that no measurable increase in the very low uranium concentrations in the<br />

solution could be observed during the entire test period (more than 15 months). If, in this case,<br />

uranyl carbonate species were produced in a layer several tens of microns thick near the surface<br />

(range of alpha particles), some of them would diffuse away and contribute to an increase of the<br />

uranium concentration in the solution. These results are confirmed by the measured levels of<br />

radiolytic oxygen, which lie below the detection limit (10 –8 M) for the oxygen sensor that was<br />

in the autoclave solution during the entire test. The same applies to any radiolytic oxygen or<br />

hydrogen peroxide: some of this would diffuse away from the surface and cause an increase in<br />

the oxygen levels, which would eventually be recorded by the oxygen electrode, since the test<br />

lasts such a long time. There is almost no gamma or beta radiation, and published data /15-23/<br />

with 5 MeV helium ions (alpha radiation) indicate that there is no influence of hydrogen on<br />

100<br />

10 mM NaCl 10 mM NaCl + 2mM HCO 3<br />

—<br />

10 —7<br />

10<br />

10 —8<br />

P H2 (bar)<br />

1<br />

0.1<br />

10 —9<br />

10 —10<br />

10 —11<br />

233 U (mol/l)<br />

0.01<br />

10 —12<br />

0.001<br />

10 —13<br />

0 200 400 600 800 1,000<br />

Time (days)<br />

Figure 15-6. Measured hydrogen pressure and 233 U concentrations in the solution as a function<br />

of time.<br />

RD&D-<strong>Programme</strong> <strong>2004</strong> 177

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