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Fuel Storage Facility Final Safety Analysis Report. Revision 1

Description: The Fuel Storage Facility (FSF) is an integral part of the Fast Flux Test Facility. Its purpose is to provide long-term storage (20-year design life) for spent fuel core elements used to provide the fast flux environment in FFTF, and for test fuel pins, components and subassemblies that have been irradiated in the fast flux environment. This Final Safety Analysis Report (FSAR) and its supporting documentation provides a complete description and safety evaluation of the site, the plant design, operations, and potential accidents.
Date: March 1, 1984
Creator: Linderoth, C.E.
Partner: UNT Libraries Government Documents Department

Aerosol research at Hanford and engineering applications to production reactors

Description: When the construction of the confinement facilities for Hanford production reactors is completed, the potential for contaminating the environment with accidentally released fission products will be greatly reduced. This was demonstrated already when rupture debris burned in the rear face area of one of the reactors in which the fog spray was installed and ready for service. The fog spray effectively prevented the spread of contamination to the ventilation equipment downstream of the rear face enclosure. Also, the commercially- available absolute filters and charcoal beds will significantly decontaminate the exhaust air, stream of all fission products except the noble gases. Laboratory studies indicate that the filter system should remove at least 50 percent of all fission product halogen vapors and over 90 percent of the particulate matter released from a nuclear incident. In addition, the charcoal beds should provide an additional 90 to 95 percent decontamination of the halogens that manage to pass through the filter. It is not expected that any of the noble gases released will be removed by this system. Laboratory studies, in general, substantiate previous estimates on the release of fission products from overheated uranium fuels. The theoretical estimates are quite accurate for the volatile and semi-volatile elements but were high for the non-volatiles. For all conditions tested in the laboratory, the measured release of strontium, barium, and zirconium was less than 0.5 percent. It was also found that most released fission products tended to deposit on any surface they contacted, a property which would cause a large fraction of fission products to be retained by the reactor and associated hardware. 11 refs., 8 figs., 6 tabs.
Date: October 24, 1960
Creator: Linderoth, C. E.; Heacock, H. W. & Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department