Study of Plutonium Oxide Powder Emissions from Simulated Shipping Container Leaks

To provide data to facilitate the predictions of PuO{sub 2} emissions through leaks in PuO{sub 2} shipping containers under accident conditions, a series of experiments was conducted using PuO{sub 2} powder and an experimental system designed to simulate a shipping container leak. Over two hundred experiments were completed. The experimental parameters investigated were the leak size/type, internal system pressure, agitation of the apparatus, leak orientation with respect to the powder location and the run time. No single parameter appeared to have any observable effect on the quantities of PuO{sub 2} emitted. However, there was an apparent dependency on the interaction between the orifice area and the internal pressure. The dependency took the form of a function of A{radical}P. Although this functional form was suggested by the data, the data were not sufficient to allow a more detailed function to be determined. The results of experiments in which the run time was variable produced the observation that changes in the run time did not result in changes in the quantities of PuO{sub 2} emitted. This observation led to the conclusion that the majority of PuO{sub 2} observed is emitted during the initial pressurization of the leak tube

Study of Plutonium Oxide Powder Emissions from Simulated Shipping Container Leaks

To provide data to facilitate the predictions of PuO{sub 2} emissions through leaks in PuO{sub 2} shipping containers under accident conditions, a series of experiments was conducted using PuO{sub 2} powder and an experimental system designed to simulate a shipping container leak. Over two hundred experiments were completed. The experimental parameters investigated were the leak size/type, internal system pressure, agitation of the apparatus, leak orientation with respect to the powder location and the run time. No single parameter appeared to have any observable effect on the quantities of PuO{sub 2} emitted. However, there was an apparent dependency on the interaction between the orifice area and the internal pressure. The dependency took the form of a function of A{radical}P. Although this functional form was suggested by the data, the data were not sufficient to allow a more detailed function to be determined. The results of experiments in which the run time was variable produced the observation that changes in the run time did not result in changes in the quantities of PuO{sub 2} emitted. This observation led to the conclusion that the majority of PuO{sub 2} observed is emitted during the initial pressurization of the leak tube

Quarterly progress report, January 1--March 30, 1979 - Study of plutonium oxide leak rates from shipping containers.

The study was initiated in October 1976, as outlined in the 189 research proposal submitted previously. Several tasks are to be undertaken in this study which, when combined, have the end objective of defining the leak rates of plutonium oxide powder from characterized leaks. Progress during the reporting period is briefly described on the following tasks: review of the literature and theoretical work relating to transmission of particles through channels; investigation of the relationship of gas flow rates, leak geometries, pressure and temperatures; measurement of the transmission of a well-characterized simulant (UO/sub 2/ powder) through leaks characterized in Task B; measurement of the fuel grade PuO/sub 2/ leaks through a standard leak incorporated into a suitable container; and investigation of PuO/sub 2/ leaks through simulated defected containers. (TFD

Quarterly progress report, October 1--December 29, 1978 - Study of plutonium oxide leak rates from shipping containers.

This program encompasses five tasks. Significant results and data are reported for Tasks C and D: Measure transmission of UO/sub 2/ powder (simulant of PuO/sub 2/) through leaks, and Measure fuel-grade PuO/sub 2/ through a standard leak in a container. 12 figures, 17 tables. (DLC

Deployment of Porous Crystalline Matrix (Gubka) Technology for Stabilizing Radioactive Standard Solutions at Fernald

Radioactive solutions requiring stabilization exist in various compositions throughout the DOE complex. Future cleanup could generate additional actinide residue solutions requiring stabilization at facilities where processing capabilities have been dismantled. Radiological laboratory standard solutions (liquid technical standards) have recently been identified at the Fernald site, which require stabilization and disposal before the laboratory facilities at Fernald can be decommissioned. The Fernald solutions consist of approximately 25 liters of acidic solutions containing isotopes of Cs, Ba, Ra, Eu, U, Am, Po, Ru, Sr, Th, Pb, Pu, and Np and in some cases small quantities of added salts. After stabilization and waste acceptance approval, the resulting waste forms will be disposed at the Nevada Test Site. This paper describes the technology and progress in using the Russian ''Gubka'' technology to stabilize the Fernald liquid technical standards for disposal by September 2002 to meet the facility D&D schedule