This report presents details about waste management practices that are being developed using remote sensing techniques to characterize DOE waste sites. Once the sites and problems have been located and characterized and an achievable restoration and remediation program have been established, efforts to reclaim the environment will begin. Special problems to be considered are: concentrated waste forms in tanks and pits; soil and ground water contamination; ground safety hazards for workers; and requirement for long-term monitoring.

This report presents details about waste management practices that are being developed using remote sensing techniques to characterize DOE waste sites. Once sites and problems have been located and an achievable restoration and remediation program have been established, efforts to reclaim the environment will begin. Special problems to be considered are: concentrated wastes in tanks and pits; soil and ground water contamination; ground safety hazards for workers; and requirements for long-term monitoring.

In designing the SCD barrel and endcap calorimeters, the inter-module connecting forces must be known in order to determine the required size and number of connecting links between modules, and in order to understand how individual modules will be affected by these forces when assembled to form a full barrel and endcap. The connecting forces were found by analyzing three-dimensional Finite Element Models of both the barrel and endcap. This paper is divided into two parts, the first part will describe in detail the results of the barrel analysis and the second part will describe the results obtained from the endcap analysis. A similar approach was used in constructing the models for both analysis.

This report discusses research on computer architecture for image processing, data analysis, and computer graphs. (LSP).

The performance of liquid centrifugation for nuclear waste partitioning is examined for the Accelerator Transmutation of Waste Program currently under study at the Los Alamos National Laboratory. Centrifugation might have application for the separation of the LiF-BeF{sub 2} salt from heavier radioactive materials fission product and actinides in the separation of fission product from actinides, in the isotope separation of fission-product cesium before transmutation of the {sup 137}Cs and {sup 135}Cs, and in the removal of spallation product from the liquid lead target. It is found that useful chemical separations should be possible using existing materials for the centrifuge construction for all four cases with the actinide fraction in fission product perhaps as low as 1 part in 10{sup 7} and the fraction of {sup 137}CS in {sup 133}Cs being as low as a few parts in 10{sup 5}. A centrifuge cascade has the advantage that it can be assembled and operated as a completely closed system without a waste stream except that associated with maintenance or replacement of centrifuge components.

In designing the SCD barrel and endcap calorimeters, the inter-module connecting forces must be known in order to determine the required size and number of connecting links between modules, and in order to understand how individual modules will be affected by these forces when assembled to form a full barrel and endcap. The connecting forces were found by analyzing three-dimensional Finite Element Models of both the barrel and endcap. This paper is divided into two parts, the first part will describe in detail the results of the barrel analysis and the second part will describe the results obtained from the endcap analysis. A similar approach was used in constructing the models for both analysis.

This report discusses research on computer architecture for image processing, data analysis, and computer graphs. (LSP).

The performance of liquid centrifugation for nuclear waste partitioning is examined for the Accelerator Transmutation of Waste Program currently under study at the Los Alamos National Laboratory. Centrifugation might have application for the separation of the LiF-BeF{sub 2} salt from heavier radioactive materials fission product and actinides in the separation of fission product from actinides, in the isotope separation of fission-product cesium before transmutation of the {sup 137}Cs and {sup 135}Cs, and in the removal of spallation product from the liquid lead target. It is found that useful chemical separations should be possible using existing materials for the centrifuge construction for all four cases with the actinide fraction in fission product perhaps as low as 1 part in 10{sup 7} and the fraction of {sup 137}CS in {sup 133}Cs being as low as a few parts in 10{sup 5}. A centrifuge cascade has the advantage that it can be assembled and operated as a completely closed system without a waste stream except that associated with maintenance or replacement of centrifuge components.