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

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6.46<br />

would be stored as a liquid, it is more probable that it would be solidified (calcined or<br />

vitrified) if an extended storage period were envisaged.<br />

6.1.2.5 Potential Impacts Over the Long Term (Postemplacement)<br />

Although repository-related human activity would be minimal once emplacement and<br />

repository decommission activities were complete, impacts could occur because <strong>of</strong> the pos-<br />

sible mobility <strong>of</strong> the molten waste material in the geologic environment. Potential events<br />

and impacts are described below.<br />

Potential Events<br />

For risk analysis purposes, the postemplacement phase <strong>of</strong> the concept is treated in a<br />

manner similar to other geologic disposal alternatives (see Section 5.6). As noted earlier,<br />

after the waste-rock matrix cooled to the point where liquid water could contact the waste,<br />

it is assumed that the waste would dissolve, and transport through the surrounding rock<br />

would be initiated. Clearly, the degree <strong>of</strong> risk calculated on this basis would be strongly<br />

site specific, and would depend on factors such as the depth <strong>of</strong> the repository, presence and<br />

location <strong>of</strong> aquifers, water quality, and sorptive properties <strong>of</strong> the rock.<br />

Possible pretreatment <strong>of</strong> the wastes to minimize potential adverse postemplacement<br />

effects would depend on the waste form as well as the geologic media characteristics.<br />

Potential Impacts<br />

Basically, the environmental considerations involved in evaluating the long-term impact<br />

<strong>of</strong> rock melting are how much <strong>of</strong> the radioactivity in the repository would reach the<br />

biosphere, when it would get there, and what its effects would be.<br />

The heat barrier effect is discussed in Section 6.1.2.3. Following total resolidifi-<br />

cation (1000 years), when the heat barrier no longer existed, most fission products would<br />

have decayed to innocuous levels. The toxicity <strong>of</strong> the residual radionuclides in the resoli-<br />

dified waste-rock matrix at that time should be significantly less than that <strong>of</strong> a typical<br />

uranium ore body from which the nuclear fuel was originally extracted.<br />

Mixing <strong>of</strong> the HLW with the molten rock, as well as the physical and chemical properties<br />

<strong>of</strong> the cooled and resolidified waste-rock matrix, would determine the rate at which radio-<br />

active species could be leached and transported by ground water. It might be possible to<br />

design some mitigating measures to significantly retard leaching rates <strong>of</strong> all or some <strong>of</strong> the<br />

radioactive species present.<br />

It is possible that the heat barrier effect would retard the start <strong>of</strong> effective leaching<br />

<strong>of</strong> radioactivity until radioactive decay had essentially eliminated the fission products as<br />

significant health hazards; thus, it might be necessary to consider only the TRU products.<br />

Transportation <strong>of</strong> radioactivity by ground water would have to be evaluated on a site-<br />

specific basis, although different scenarios could be postulated to obtain order-<strong>of</strong>-<br />

magnitude estimates <strong>of</strong> the time required for radiation to appear in the biosphere and <strong>of</strong> the<br />

concentrations <strong>of</strong> radioactive species that would be present in the water. In modeling the

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