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.

Report presenting an investigation of 57 experimental tubular designs embodying adjacent fuel-rich and air-rich regions and axial staging of the fuel introduction at simulated high-altitude conditions. Results regarding the development of pilot, development of secondary-air admission sleeve, development of final configuration, and performance of best configuration are provided.

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.