This report, dated March 22, 1954 details work procedures for the 200- West Area at HAPO. Topics discussed include emergency procedures, safety and housekeeping practices, policies and procedures, instruments and equipment located at the 622 tower, instruments and equipment located offsite, observational procedures, form entries, and card punching, and weather forecasting.

None

None

None

The major design features, nuclear characteristics and performance data for a nuclear fueled central station power plant of 75,000 kw net capacity are presented. The heat source is a Na cooled graphite moderated reactor. The design of the reactor takes full advantage of the experience gained to date on the Sodium Reactor Experiment (SRE); the plant described here is a straightforward extension of the smaller experimental SRE, which is now under construction. The fuel elements are made up of rod clusters and the moderator is in the form of Zr canned graphite elements. The performance of the reactor has been based on conservative temperatures and coolant flow velocities which result in a plant with "built-in reserve." Thus, as experience is gained and anticipated improvements in reactor fuel elements and construction materials are proven, the performance of the plant can be increased accordingly. Two reactor designs are described, one for operation with slightly enriched U fuel elements and the other for operation with Th--U fuel elements. The associated heat exchangers, pumps, steam, and electrical generating equipment are identical for either reactor design. An analysis of turbine cycles describes the particular cycle chosen for initial operation and discusses a method by which …

This document discusses studies of the behavior of uranium metal as a fuel element which previously have been hampered by the lack of understanding of the nature of radiation damage to the crystal structures. With the aid of the double crystal x-ray spectrometer, samples from irradiated fuel elements which had receive total exposure of 150 MWD/T and 1,000 MWD/T were studied and gross radiation damage was not present. Although these findings are of a preliminary nature, they are well in agreement with theoretical calculations in which the equilibrium concentration of displaced atoms at temperatures above 200{degrees}C would be extremely low. Assuming this to be the case, most of the crystallographic imperfection induced by pile radiations must have been annealed out of the metal studied. On the basis of this work it would seem quite likely that some fundamental facts about the nature of radiation damage could be learned by keeping the temperature low. This production test is designed so as to give information regarding the crystal structure damage where the uranium temperature during irradiation and post-irradiation operations is kept below 35{degrees}C.

The Uranium Recovery Plant, over the life of the operation, will be required to attain maximum recovery of stored uranium and to produce aqueous waste in a volume equivalent to the volume of stored uranium waste which, after acidification, constitutes the feed stream for the process. Due to variations in the composition of the feed stream, the waste stream does not consistently have a volume equivalent to the volume of the stored metal waste. This variation volume equivalence impedes tank farm scheduling because of the necessity for return of the process waste to underground tanks made available by the recovery operations. A plant test, using nickel ferricyanide to remove Cs-137 and Sr-90 from the Uranium Recovery Plant wastes has been completed and this memorandum has been prepared to summarize and report the results obtained from this test.