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Euradwaste '08 - EU Bookshop - Europa

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though with a slow rate. The data indicate that only some hundred μm of the fuel will corrode in<br />

1 million years.<br />

Whether or not radiolytic effects are detrimental to spent fuel stability depends to a large extent<br />

on the time of container failure. In the accidental scenario of container failure within the first<br />

centuries after disposal, radiolysis may prevail. In this case, bromide concentrations in<br />

groundwater might make the stabilizing hydrogen effect insignificant.<br />

It was long thought that radiolysis will provide oxidizing conditions at the fuel surface, even in<br />

overall reducing environments. This has motivated various studies of secondary phase formation<br />

of U(VI) solid phases like phosphates or studtite in NF-PRO. It has now been shown that in<br />

hydrogen saturated environments reducing conditions will remain dominant directly at the fuel<br />

surface. Therefore, only U(IV) containing alteration products are expected to form.<br />

5. Remaining uncertainties and recommendations for the future<br />

5.1 Vitrified waste<br />

The integrated tests and modelling have shown that the key mechanisms allowing a qualitative and<br />

semi-quantitative description of the glass dissolution processes are known. The application to specific<br />

disposal sites will have to take into account the specific characteristics of the disposal design<br />

and host rock characteristics. Glass dissolution in cement based near-field conditions has not been<br />

studied in NF-PRO. The related phenomenological description and process understanding still<br />

needs more work than for the other systems at neutral pH. In all reference concepts, the overpack is<br />

expected to last much longer than just the thermal phase, and thus will provide a non-negligible<br />

safety reserve. The formation of metallic corrosion products does not fundamentally change the<br />

glass dissolution, because sorptions on metallic corrosion products and on bentonite are similar.<br />

The current models predict faster glass dissolution as long as the magnetite layer is not saturated<br />

with silica, but the total sorption capacity of the magnetite is too low to have an important effect on<br />

the total glass life time. Detailed modelling of the interactions between glass and corrosion products<br />

is not yet possible, but a detailed description would most probably not lead to significantly shorter<br />

life time predictions. Moreover its application in the safety assessment may be not straightforward<br />

because the formation of a thick corrosion product layer is unlikely. Instead, iron rich clay minerals<br />

are expected to be formed in the absence of glass [5]. The long term effect of metallic corrosion<br />

products is probably negligible, because of saturation of the sorption sites by silica. Furthermore,<br />

site densities of magnetite used in the experimental studies are expected to be much higher than in<br />

reality, since dense layers of very little porosity will be formed. In the reference source term model,<br />

the maximum dissolution rate is applied as long as the magnetite layer is not saturated. Omitting<br />

this magnetite layer (i.e. replacing it by a bentonite layer) would imply a longer glass life time.<br />

Hence the reference source term model is conservative in this respect. One should take this into account<br />

when setting future research priorities. Nevertheless, the programme has suggested two potential<br />

long term effects of metal corrosion that may be worthwhile further investigation: (1) the<br />

precipitation of iron rich silica phases partially replacing the magnetite layer (this may include also<br />

coprecipitation phenomena), and (2) a local pH increase due to actively corroding iron.<br />

Apart from this, a better characterization of the long term dissolution processes and measurements<br />

in conditions more representative for specific disposal designs are still necessary.<br />

The programme has given further evidence that retention of specific radionuclides in secondary<br />

phases is likely to contribute to the overall safety, but this process is not included in the reference<br />

source term model. Including it would require much more research in this area, taking into account<br />

the different conditions depending on the disposal site and design.<br />

180

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