We have reviewed the problem of recovering I{sup 131} from the Separations Process and conclude that recovery is entirely feasible. This report contains recommendations for I{sup 131} recovery offered for consideration and are based on a technical study.

This report discusses the Production Test 105-2-P (Supplement A) -- Activity of Pile Discharge Water. Previous studies of pile discharge water have shown that one of two processes is responsible for the large but variable amount of Mn{sup 56} activity present in the water. One process is the production of Mn{sup 56} by the reaction Mn{sup 55} on manganese impurity in the water. The amount of such impurity has been shown to be too small to produce the observed amount of Mn{sup 56} unless the mean irradiation time is increased by a large factor due to temporary sticking of manganese on the surfaces in the tubes. The other process is the production by the reaction Fe{sup 56} on iron in the film. The present production test was designed to determine which of these processes is responsible for the troublesome Mn{sup 56} activity and to what extent the activity is increased due to sticking of manganese or iron in the tubes. 4 figs.

This document details technical activities in the 100, 200, 300 areas as well as activities in the chemical development, statistical studies, and Laboratories Departments for the period of October 6 through October 12, 1946. (FI)

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Tests made prior to beginning operation of the 100 Areas showed that the cooling water had a tendency to deposit a film upon the slug and tubs surfaces. This film would manifest itself as an increase in the pressure drop through the tubes and its most serious affect would be the resultant decrease in the slug to water host transfer coefficient which would increase the slug surface temperature, causing greatly accelerated corrosion rates. It was thus proposed to study film formation an a production test. This report discusses this test.

This technical progress report details 100 Area activities for the time period of July 16 through July 22, 1946.

Operation of the D and F Piles is reported. Other items reported are: general; water, corrosion and engineering (graphite expansion).

This technical progress report details 100 Area activities for the time period of August 13 through August 19, 1946.

This technical progress report details 100 Area activities for the time period of May 14 through May 20, 1946.

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Reported are: physics (B pile, D pile, F pile, general physics); and water, corrosion and engineering (process water control and pressure drop studies, purging studies, removal of process tube B-3671).

This memorandum provides an estimate of the life of manufacturing piles.

In August 1946 it was discovered that two effluent lines near the Columbia River at Hanford were damaged. The upstream effluent line has broken off 37 fact from the shoreline and the downstream effluent line had been bent and partly broken seventeen feet from shoreline and has swung downstream to a point about 50 feet from shorelines. This study was made to determine how fast and in what fashion the temperature of the effluent water is dissipated in the Columbia River under the present conditions and to compare this to a previous survey made when the effluent lines were believed to be in their original position.

This report details 100 Area reactor operation for the time period of May 21 through May 27, 1946.

Reported are: physics (B Pile, D Pile, F Pile, general physics); and water, corrosion and engineering (process water control and pressure drop studies, corrosion, graphite expansion).

This weekly technical progress letter details 100 Area activities for the week of May 28 through June 3, 1946.

During this period the B Pile operated at its assigned power level of 25 MW below rated level, except for 10 hours on January 5. The operating level of the D Pile remained at 25 MW below rating. The rate gain in excess reactivity during equilibrium operation has been about 1.8 inhours/day. On January 1, the power level of the F Pile was dropped to 25 MW below rating from its previous rated level. Rod A was in a favorable position to make a determination of the reactivity coefficients at the time. The data does indicate an upper limit of {minus}0.21 ih/MW for the metal coefficient. An overall coefficient of 0.20 ih/MW was obtained. The unit was shut down on January 3 for discharge of 129 tubes of metal. A summary of the present reactivity states of the B, D, and F Piles are given. Iron content of process water for the three piles is also given.

It was agreed during a meeting on July 10, 1945, investigation should be made to determine how fast and in what fashion the temperature of the effluent water from the 100 Areas is dissipated in the Columbia River. A preliminary report on these investigation was issued March 1, 1946: it discussed the testing techniques developed and the results of a survey made at the 100-B Area. Following a review of the data and tentative conclusions resented therein, it was agreed to extend the survey using similar technique: to the D and F Areas, and to determine if the tentative conclusions were substantiated.

This document contains information concerning the dissolved oxygen content of the Columbia River and Yakima Rivers near the Hanford Production Reactors on May 3, 1946. Data is presented in graphed form with weekly variations plotted.

Progress is reported on the topics of extrusion and canning. The information on canning is broken down into: Production test 313-74-M, studies of aluminium cans, selection of surface rejection standards, thorium, and the effect of high and low tin in bronze on tin carry-over to canning bath.

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This report from the reactor fuel manufacturing facilities at Hanford highlights extrusion, canning, and welding operations. Processing of thorium and bismuth is discussed. Radiography of fuels revealed voids that conformed underweight reject measurements.

The weekly progress for D and F piles is given. Status of the test to determine the cause of white deposits on the horizontal control rods of the F pile is given. Also discussed are studies of process water control and pressure drop, corrosion, and graphite expansion. Test results indicate that graphite expansion has not seriously limited discharge of process tubes.

At the shutdown of the B Pile, 269 active tubes were discharged and ten poison columns were charged. As a result, the pile was let considerably below critical. The present test described in this report was set up to develop methods of detecting possible changes in reactivity by periodic measurements of neutron flux in the shutdown pile. The irradiation of indium foils in an empty process tube was found to provide a satisfactory method of monitoring the shutdown pile, and was sensitive than the proportional counter with was also tried. The accuracy with which the subcritical condition can be determined is roughly 20%. The uncertainty is due mostly to the irregular arrangement of metal and poison in the unit and the resulting difficulty in representing the neutron flux mathematically.