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Salt Disposal of Heat-Generating Nuclear Waste

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SAND2011-0161<br />

Unlimited Release<br />

Printed January 2011<br />

<strong>Salt</strong> <strong>Disposal</strong> <strong>of</strong> <strong>Heat</strong>-<strong>Generating</strong> <strong>Nuclear</strong> <strong>Waste</strong><br />

Frank D. Hansen and Christi D. Leigh<br />

Frank D. Hansen<br />

Christi D. Leigh<br />

MS 0751 Org 6914 MS 1395 Org 6212<br />

Sandia National Laboratories<br />

Sandia National Laboratories<br />

P.O. Box 5800<br />

4100 National Parks Highway<br />

Albuquerque, NM 87185-0778 Carlsbad, NM 88220<br />

ABSTRACT<br />

This report summarizes the state <strong>of</strong> salt repository science, reviews many <strong>of</strong> the technical issues<br />

pertaining to disposal <strong>of</strong> heat-generating nuclear waste in salt, and proposes several avenues for<br />

future science-based activities to further the technical basis for disposal in salt. There are<br />

extensive salt formations in the forty-eight contiguous states, and many <strong>of</strong> them may be worthy<br />

<strong>of</strong> consideration for nuclear waste disposal. The United States has extensive experience in salt<br />

repository sciences, including an operating facility for disposal <strong>of</strong> transuranic wastes. The<br />

scientific background for salt disposal including laboratory and field tests at ambient and<br />

elevated temperature, principles <strong>of</strong> salt behavior, potential for fracture damage and its mitigation,<br />

seal systems, chemical conditions, advanced modeling capabilities and near-future<br />

developments, performance assessment processes, and international collaboration are all<br />

discussed. The discussion <strong>of</strong> salt disposal issues is brought current, including a summary <strong>of</strong><br />

recent international workshops dedicated to high-level waste disposal in salt.<br />

Lessons learned from Sandia National Laboratories’ experience on the <strong>Waste</strong> Isolation Pilot<br />

Plant and the Yucca Mountain Project as well as related salt experience with the Strategic<br />

Petroleum Reserve are applied in this assessment. <strong>Disposal</strong> <strong>of</strong> heat-generating nuclear waste in a<br />

suitable salt formation is attractive because the material is essentially impermeable, self-sealing,<br />

and thermally conductive. Conditions are chemically beneficial, and a significant experience<br />

base exists in understanding this environment. Within the period <strong>of</strong> institutional control,<br />

overburden pressure will seal fractures and provide a repository setting that limits radionuclide<br />

movement. A salt repository could potentially achieve total containment, with no releases to the<br />

environment in undisturbed scenarios for as long as the region is geologically stable. Much <strong>of</strong> the<br />

experience gained from United States repository development, such as seal system design,<br />

coupled process simulation, and application <strong>of</strong> performance assessment methodology, helps<br />

define a clear strategy for a heat-generating nuclear waste repository in salt.<br />

iii

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