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

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5.8<br />

releases so that substantial nuclide decay occurs before entering the geologic system where<br />

the natural barriers would prevent or delay releases to the biosphere.<br />

5.1.2.2 <strong>Waste</strong> Packages Components<br />

Components <strong>of</strong> a generalized waste package were shown in Figure 5.1.2. The following<br />

discussion addresses each component separately; however, it is the performance <strong>of</strong> the entire<br />

system <strong>of</strong> components taken as a whole that is <strong>of</strong> most importance in the final analysis.<br />

<strong>Waste</strong> Form<br />

The waste forms include all radioactive materials that may potentially be sent to deep<br />

geologic repositories, and are divided into three major categories: spent fuel, high-level<br />

waste and TRU waste forms, which are described in more detail in Sections 4.3.2, 4.3.3,<br />

and 4.3.4, respectively. The current primary emphasis on waste package design is for spent<br />

fuel and for HLW, the reference waste forms considered throughout the following discussion.<br />

Due to their high radiation levels and heat generation, spent fuel and HLW place the most<br />

stringent requirements on the waste package. However, when most <strong>of</strong> the fission products<br />

have decayed (after a few hundred years), the properties <strong>of</strong> the TRU waste become dominant.<br />

The waste form is an inert solid designed to be chemically, thermally and radiolyti-<br />

cally stable. The waste form itself is the first containment barrier for the waste.<br />

Canister<br />

The canister provides physical containment for the waste forms and thus isolates the<br />

waste from near-field surroundings. The extent to which the canister can delay or minimize<br />

waste-water interactions is important. Moreover, the canister is expected to provide physi-<br />

cal protection during interim storage, transportation, handling, emplacement, and any waste<br />

retrieval operations that may be required. The canister material chosen must be compatible<br />

with the waste form. The ductility, weldability and impact resistance <strong>of</strong> metals make them<br />

primary candidates as canister materials.<br />

High-level waste forms will generally fill the canister 80 to 90% full. The remaining<br />

space will be occupied by air. Stabilizer materials are being considered for use in spent<br />

fuel canisters. Gaseous stabilizers, such as helium, have been considered from the stand-<br />

point <strong>of</strong> providing a heat transfer medium without causing chemical or mechanical attack on<br />

the spent fuel/cladding assembly or the canister. Particulate or solid stabilizers, such<br />

as lead, glass, clay, or sand, can provide additional functions, including maintaining the<br />

position <strong>of</strong> the spent fuel within the canister; preventing canister collapse under litho-<br />

static pressures; acting as a corrosion resistant protective barrier; improving heat trans-<br />

fer; increasing radiation attenuation; and enhancing nuclide sorption.<br />

Overpack<br />

The overpack is similar in principle to the canister. An overpack <strong>of</strong>fers several<br />

options to the package designer: it may function as a redundant canister, applied (if<br />

necessary) for all stages <strong>of</strong> package handling, transportation, and emplacement; it can<br />

exhibit corrosion or mechanical properties superior to those <strong>of</strong> the primary canister,

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