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C. WPu Disposition Through Vitrification with HLW
Pages 70-72

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From page 70...
... In the United States borosilicate glass has been the primary choice; the boron in the glass is a useful component to lower criticality risks, and the glass is heat resistant. For the purpose at hand, the final product of the vitrification process would be a glass log in which the plutonium and the other radioactive wastes are dissolvent or suspended, cast into a cylindrical stainless steel shell.
From page 71...
... A waste form could also be clevelopec} specifically for the plutonium disposition mission with a radiation protection barrier from highly radioactive Cesium-137, which is available in the United States. This possibility would still require substantial R&D and costs.
From page 72...
... 72 H0X robe. It is therefore believed tab licensing problems in the United States far the glass _ mercia1 reactors.

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