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RD&D-Programme 2004 - SKB

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238 U<br />

237 Np<br />

239 Pu<br />

Concentration, mol/l<br />

10 —7<br />

10 —8<br />

10 —9<br />

10 —10<br />

10 —11<br />

10 —6 0.5 MPa (H 2 +0.03%CO 2 )<br />

0.5 MPa Ar<br />

144 Nd<br />

153 Eu<br />

10 —12<br />

0 100 200 300 400 500<br />

Leaching time, days<br />

Figure 15-3. Measured concentrations of actinides (U, Pu, Np) and lanthanides (Eu, Nd) as a<br />

function of the time for leaching of spent fuel powder in a 10 mM NaCl, 2 mM NaHCO 3 solution<br />

and either 0.5 MPa hydrogen mixed with 0.03 percent carbon dioxide or only 0.5 MPa argon.<br />

concentrations of actinides and lanthanides in solution samples taken at different points in time<br />

(Figure 15-3) show similar values as in the stainless autoclave. Investigation of the behaviour<br />

of redox-sensitive nuclides such as uranium, technetium and neptunium during the first days<br />

(which were missed before) showed that their already low starting concentrations declined with<br />

time. This suggests that they are reduced, which is also found in other studies /15-18, 15-19/.<br />

The fact that only low concentrations of radionuclides were measured in autoclave solutions<br />

/15-19/ indicates that this reduction takes place at the surface of the fuel.<br />

Another goal of the study was to follow and understand what happens with oxygen that is<br />

generated by radiolysis of water in hydrogen-saturated solutions. A gas sample taken from<br />

the autoclave after 356 days and analyzed by mass spectrometry showed oxygen concentrations<br />

below the detection limit (approx. 50 ppm or 5·10 –8 mol/l). The same results were found<br />

in another, independent study /15-20/. When these data are compared with the high oxygen<br />

concentrations measured in similar tests and during similar time periods /15-21/ but under an<br />

argon atmosphere (Figure 15-7), plus the extremely low concentrations of uranium and other<br />

experimental observations, it can be concluded that radiolytic oxidants must be consumed by<br />

hydrogen under such conditions and that no measurable oxidative dissolution of fuel occurs<br />

/15-17/. This is confirmed by an analysis of the released fraction of fission products, such as<br />

strontium-90 (Figure 15-4). This was not noticed in stainless autoclaves, and one explanation<br />

may be that despite all efforts to avoid contamination with air, the gas analysis showed that there<br />

was nitrogen in the autoclave /15-17/. But since corresponding oxygen quantities would have<br />

caused a nearly tenfold higher increase of the concentrations of strontium-90 if the oxygen had<br />

only been consumed to oxidize the fuel surface, this indicates that dissolved hydrogen consumes<br />

not only radiolytic oxidants, but also the oxygen from air contamination.<br />

These and other experimental data suggest that hydrogen must be activated under experimental<br />

conditions in order to be able to consume oxidants from radiolysis and oxygen from air<br />

contamination, and cause reduction of radionuclides.<br />

There are two possible ways to activate hydrogen under experimental conditions: either by<br />

reactions with radicals from radiation-induced radiolysis, or by reaction with fuel surfaces<br />

(uranium dioxide surfaces and/or metallic particles in the fuel).<br />

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

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