The following document analyzes radioactive spot contamination in and around the T and B Plant Areas.

The following document was done under the auspices of the U.S. Atomic Energy Commission with the intention of analyzing air core cryogenic magnet coils and its usage in fusion research and high energy nuclear physics applications.

Abstract: "Preliminary design and experimental work aimed toward fabrication of large magnet coils with encapsulated sodium conductors is outlined. Aspects of cooling cycles are discussed along with heat transfer, thermal stability, and the mechanical reinforcement of such coils."

This report for October, 1947 describes progress regarding ore dressing and pyrometallurgical studies, chemical work on phosphates, chemical work on shales, and analytical work.

Design Test Request PR-20 Calandria Characteristics, outlined the need for experimental data concerning the performance of the calandria under transient conditions. Test data was required to confirm that the moderator dump system would drop the level the required 24 inches in less than one second. The original calandria dump chamber design was modified until the criteria was met. This information is recorded in HW-58333, Interim Report, Design Test PR-20, Calandria Characteristics, which lists the drop for the first 24 inches only.

A set of 69 pile yield curves for the production of plutonium, americium, and curium isotopes in a neutron flux of 5 x 10<sup>14 cm<sup>-2 sec<sup>-1 is given. The differential analyzer of the University of California Radiation Laboratory was used in obtaining the curves. The curves are given also on log-log plots for comparison.

Leaching of high carbonite Belgian Congo uranium ores with sulfuric acid and recovery of the uranium from leach solutions by uranous phosphate precipitation are described.

During this quarter, the Hanford Atomic Products Operation reorganized with the elimination of the Radiological Sciences Department as a separate organizational entity. The new structure which was effective on September 1, 1956, is outlined in this report to indicate the new relationships.

The purpose of the test is to determine the reason for the decreases in the liquid levels of the reference chambers serving the reactor plant remote liquid level indicators. The remote gages and the local liquid level gages agreed closely for the Reactor Plant Component Cooling Water Expansion Tank and the Coolant Discharge and Vent System flash tank and blow-off tank. There appeared to be no loss of water from the D/P cell reference chambers for these two systems over the period of the test. There was no definite indication of leakage from the Valve Operating System reference chamber, however, the differences between remote indicator readings and the sight glass readings are attributed to sticking of the ball check valve on the upper sight glass, inaccuracy of the readings and instrument error. It is recommended that he lower shut-off valve on the upper sight glass be cleaned and reopened prior to reading the sight glass to ensure that the ball check valve is not stuck in the closed position. No lead age was found in any of the level indicating systems.

The purpose of the test was to determine the neutron flux level in a BF3 counter well during the second performance of DL-S-225. The measured activity of the irradiation brass bolt was due entirely to the radioactive decay of Zn65. The thermal neutron flux in the BF3 counter well during the second 1000 hour run was calculated to be 2.5 x 10(9) neutrons/cm2 sec.