Americium (atomic weight 241) grows into plutonium as a result of the 13-year half-life beta decay of Pu{sup 241}. An appreciable quantity of Am{sup 241} has.grown into the scrap that accumulated following shut-down of the Recuplex facility, and which will be processed during the initial period of operation of the plutonium reclamation facility. Current interests in trans-plutonium research and in isotopic heat sources make it desirable to consider the recovery of this Am{sup 241}. The americium contained in scrap that is processed through the reclamation facility should appear almost quantitatively in the aqueous waste stream (CAW). Subsequent processing of the CAW through the DBBP extraction column (CW) of the waste treatment facility should result in further separation of plutonium and americium by extracting some of the plutonium while most of the americium remains in the aqueous waste stream (CWW). The fact that a low free nitric acid concentration will favor the extraction of americium into TBP-type solvents can be used to recover americium from the large volume, high salt concentration CWW stream. The flowsheets in this document present the chemical conditions for effecting this recovery.

Salt wastes from the Redox solvent extraction process have been routed to the 241-SX tank farm for storage since May 21, 1954. Tanks in this farm contain wastes from three types of irradiated uranium processing: (1) low (approximately 250 MWD/T) and (2) high (approximately 600 MWD/T) natural uranium; and (3) E-metal. It is estimated that approximately 1.6 Kgs of Am-Cm, 17 Kgs of Np-237, 20 Kgs of Pu and 8 tons of uranium are present in the sludges from wastes generated through 4-30-64. A total of 12.1 Kgs of the 29.1 Kgs of Np-237 estimated has been recovered or is present in the Redox Np-237 accumulation cycle as of 4-30-64. Because of the potential for unmeasured losses (such as Pu or U precipitates) the total plutonium and uranium may exceed the quantities stated herein. A breakdown of the estimates by tanks is provided.

This research and development report details activities of the Irradiation Processing Department during the month of August 1965.

The Redox acid precycle flowsheet which has been in use since November of 1959 vas adopted to provide neptunium recovery. Although neptunium recovery on this flowsheet has been satisfactory, several problems have been encountered. Among these are: marginal uranium decontamination, increased hexone degradation and increased corrosion of precycle piping and equipment. To circumvent these problems an acid-deficient precycle flowsheet was proposed. In August, 1964, following replacement of the 1A Column and the D-14 backcycle concentrator, the Redox plant was started up on this flowsheet. Neptunium, which left the 2A Column in the waste stream was recovered by processing the waste stream through the 1S Column on an acid flowsheet. The neptunium, extracted in the 1S Column was stripped in the 10 Column and routed to the D-14 backcycle concentrator in the 10W stream. Using this flow pattern it was planned to accumulate neptunium in the D-14 and F-8 vessels-and the 1A, 1S and 10 Columns. Inadequate stripping of neptunium in the 10 Column with resultant neptunium losses to the waste stream necessitated abandoning this flow pattern and the neptunium stream from the 1S Column has been routed to the 2E Column with the 1A Column product stream. Neptunium is presently …

Brief summaries are given for the status of activities in the following areas: Reactor fuels; Reactor engineering; Reactor physics; Radiological engineering; Process standards; Process change authorization; Fuel failure experience; Pile physics assistance; Process physics studies; Testing of fuel elements; and Testing and irradiation services.

Using a Mechrolab Vapor Phase Osmometer and a Hallikainen Automatic Membrane Osmometer the number-average molecular weight of two samples of dimethylpolysiloxane - 2300 and 8000 cstk - as well as samples made by mixing the two previously mentioned materials were determined.

Water for fire and sanitary use in the older reactor areas is provided by pumps located in the 183 building of each particular area. Each area has two electrically driven pumps for normal use and two steam driven pumps in case of power failure. Distribution within an area is through an underground main loop with laterals to buildings and fire hydrants. When the DR, F and H Reactors are deactivated, fire and sanitary water in each area is still necessary for protection of the area and for certain peripheral facilities which can not be moved immediately to other locations. In D area, deactivation of the DR Reactor will not effect the fire and sanitary water system but in F and H areas, deactivation of the reactors will cut off the source of fire and sanitary water unless 181 river pumps, 182 filter plants and the 184 power houses are kept in operation. The purpose of these design criteria is to describe the scope of work and operational and technical requirements for conversion of the export water line between D and F areas to a fire and sanitary main to supply water from D area to F and H areas. 2 …