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

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subsequent precipitation <strong>of</strong> minerals. Permissible temperature rises <strong>of</strong> 80 and 28°C for<br />

K.3<br />

stagnant aquifers 30 and 90 m deep, respectively, have also been proposed (Science Applica-<br />

tions, Inc. 1976).<br />

* Near-Field Considerations<br />

Rooms must be accessible at the end <strong>of</strong> the retrievability period to allow safe entry<br />

for the removal <strong>of</strong> canisters with the same equipment used to emplace them. Calculated room<br />

closures <strong>of</strong> less than the limit imply that the repository will generally remain structur-<br />

ally stable throughout the retrieval period, although some local failure controlled by<br />

local rock conditions not accounted for in the analysis may occur.<br />

In addition to thermal loading, the closure <strong>of</strong> rooms in a salt repository will depend<br />

on the depth <strong>of</strong> the repository; this relates directly to stress and mine-geometry parameters<br />

such as the percent extraction <strong>of</strong> salt and pillar width-to-height ratios. Room closure cal-<br />

culations appear to be relatively insensitive to stratigraphy provided that the salt near<br />

the burial horizon is at least hundreds <strong>of</strong> feet thick.<br />

* HWL Temperature for Glass, 500 0 C<br />

Typical borosilicate waste glasses have a transition temperature <strong>of</strong> about 500'C, with<br />

a slightly higher s<strong>of</strong>tening temperature. Migration <strong>of</strong> heavy, separate phases in the glass<br />

might occur above the s<strong>of</strong>tening temperature. Significant increases in cracking and in<br />

leach rates have been observed in test glasses heated for a few months in the range 5000to<br />

800°C. Additional information is available for solid waste temperatures <strong>of</strong> glass, calcine,<br />

and sintered glass ceramic (Jenks 1977, Mendel et al. 1977).<br />

* Spent Fuel Pin Temperature, 300°C<br />

A study <strong>of</strong> possible failure mechanisms during dry storage <strong>of</strong> spent fuel assemblies<br />

sealed in carbon steel canisters recommended a maximum allowable cladding temperature <strong>of</strong><br />

380 0 C based on stress rupture considerations. Some uncertainty regarding possible stress<br />

corrosin cracking was noted. To be safe, a 300°C maximum fuel pin temperature is specified<br />

here.<br />

* Canister Temperature, 375°C<br />

Austenitic stainless steel, probably 304L, proposed to be used in HLW canisters<br />

undergoes changes in structure during long-term exposure in air at temperatures in the<br />

range 400 to 900 0 C. The observed effect is an increased susceptibility to stress cracking<br />

when the steel is subsequently exposed to aqueous solutions (Jenks 1977).<br />

* Rock Temperature, 250 0 C to 350°C<br />

Behavior <strong>of</strong> salt deposits at temperatures up to 250 0 C are believed to be predictable.<br />

Laboratory tests (Jacobsson 1977) indicate that unconfined rock-salt samples from several<br />

locations begin to decrepitate (disaggregate) in the 2600to 320°C range, but samples from<br />

other locations show no decrepitation when heated to 400°C. Decrepitation is undesirable<br />

because it reduces thermal conductivity <strong>of</strong> the salt in the vicinity <strong>of</strong> a waste package and<br />

could lead to undesirable higher temperatures in the container and waste. In the case <strong>of</strong><br />

bedded salt, decrepitation may release brine, which is also undesirable.

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