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A detailed description of the processing of pitchblende ores used at the Port Hope, Canada, refinery is given including both the recovery and purification of U and Fu. The health hazards present in the processing are discussed, and recommendations are made which will insure adequate health protection. (L.T.W.)

A scheme of glucose degradation has been validated by the use of intermediates of known isotopic composition. In this scheme: glucose {yields} lactic acid {yields} CO{sub 2} (C-3,4) + acetic acid {yields} CO{sub 2} (C-2,5) + acetone {yields} iodoform (C-1,6) + acetate (C-1,6; 2,5), it was found that (a) in the oxidation of lactic acid, approximately 4.7% of the acetic acid was oxidized to CO{sub 2}; and (b) under the conditions prescribed, BaCO{sub 3} from the degradation of Ba acetate contained approximately 1.5% of the activity of the methyl group.

This quarterly report discusses the following topics: (1) the metabolic properties of plutonium and allied materials; (2) biological studies of radiation effects; (3) biological effects of radiation from external and internal zones; and (4) health chemistry.

Results of type II UF/sub 6/ centrifuge operation are presented. Data from this type operation in a single unit are useful in predicting the operation of a number of centrifuges in cascade. (J.R.D.)

The procedure for estimation of heats of formation of compounds is illustrated by discussion of compounds of several of the elements of the actinide series. The procedure is particularly suited for lanthanide and actinide elements because of the similarity of the ionic radii and types of bonding.

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In the treatment of carnotite concentrates, sodium diuranate was prepared by acidifying tricarbonate liquors to eliminate carbon dioxide, and then precipitating the sodium salt by the addition of caustic. Direct precipitation of uranium by the addition of caustic to tricarbonate liquors was used when pitchblende ores were processed, because this procedure was more effective in giving a product with a low molybdenum content. Tests of this method in the laboratory and Pilot Plant indicated that low uranium losses (0.2 to 0.3%) would be encountered with typical liquors if 1.7 to 2.0 lbs of caustic were added for every pound of uranosic oxide in solution. Since losses as high as 3% were incurred in plant operations, further work was undertaken, in an effort to reduce the uranium concentration in the waste liquors.

In the ether extraction process, as originally developed, purified uranium dioxide was obtained by evaporation and calcination of the uranyl nitrate solution, followed by calcination of the resultant UO{sub 3}. It was suggested that an alternate procedure might be developed, involving the precipitation of uranium from the nitrate solution as ammonium diuranate. This material could then be calcined to uranosic acid, or reduced directly to the dioxide. It had already been established that ammonium diuranate could be precipitated completely from uranyl nitrate solutions. Experiments were carried out to determine whether a basic nitrate, analogous to a known sulfate salt, would be formed in the process. Both direct reduction of the diuranate to UO{sub 2} and calcination to uranosic acid were investigated to determine the physical characteristics and residual nitrogen of the resultant brown oxide.

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The Purpose of this manual is to describe preparation of bismuth powder for use in process operations. Bismuth powder is to be prepared in Room 232 of ``T`` Building where all necessary apparatus is installed.

On February 4 at a conference in T.C. Gary`s office attended by Messrs. Wood, Gary, H.T. Daniels, Burns and C.R. Johnson, the design of the strap plates on the front and rear shields of the pile was discussed from the standpoint of welding technique in the field. Discussion of the design centered about the plug welding of the plates to the Laminated blocks and the ability of the field to perform this work properly. It was decided that welding specialists should be consulted prior to the beginning of the actual field erection in order that the best technique could be employed to guarantee good workmanship. It was agreed that a conference with such specialists should embrace both the features of the design as well as the practical phases of welding itself. This report provides details of this conference.

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Activities covered in this report for the month of January are as follows: (1) power coefficient test of the F Pile; (2) control rod calibration; (3) investigations into reactivity gains possible by zoning the pile for metal charging; (4) polonium production under emergency conditions: (5) analysis of process tube ion chamber failures; (6) measurements of the thermal neutron flux in various pockets of the E Test Hole of the F Pile; (7) reactivity balance of each of the operating piles at beginning and end of this report period; (8) graphite studies; (9) pile shielding; (10) radiation measurements on a simulated D-R rod guide and rod; and (11) calculation of radioactive isotopes expected in cooling water.

The total power output of a unit may be represented by the power output of the most productive tube or tubes multiplied by a quantity designated as the ``number of effective tubes.`` The number of effective tubes observed at 105-D under two different arrangements of poisoned columns has been compared with values of this quantity calculated from theory. It was found that in each case the observed number of effective tubes was about 5% less than the ideal number obtainable by an optimum arrangement of the poison. In the case in which two poisoned columns in the pile took up 110 ih it was found that the loss consisted of 2% due to the necessary presence of a control rod in the pile and 3% due to the fact that the actual arrangement of the poison was not the optimum one. In the case in which a single, off center, poison column took up 60 ih, it was found that very little of the loss was due to the presence of the control rod and almost all of it was due to the eccentric position of the P-column. As a further result of this study, it was found that, apart …

This site description of the Hanford Reservation from February 1943 gives size, topography, geology, population, water supply, railroad, highway, power, meteorological, and valuation information. Maps are included.

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This document is a letter written February 24, 1944, concerning solids found when evaporating water from the Columbia River.

This technical progress letter contains reports from six Technical Department divisions at the Hanford Engineer Works for February 9, through February 15, 1947. The six reporting divisions are: 100 Areas, 300 Area, 200 Areas, Chemical Development, Laboratories, and Statistical Studies.

This technical progress letter contains reports from six Technical Department divisions at the Hanford Engineer Works for February 16 through February 22, 1947. The six reporting divisions are: 100 Areas, 300 Area, 200 Areas, Chemical Development, Laboratories, and Statistical Studies. (JL)

Despite the fact the adequate data from long-term, chronic experiments on the effects of Po{sup 210} are not available, some sort of a working figure for the maximum permissible body content of polonium is desirable. As described herein, calculations involved in determining the permissible body content of polonium generally fall into three classes. 1. Comparison of X-ray and polonium toxicity and application of an acceptable X-ray tolerance figure. 2. Assumption of a most sensitive organ and computation of the critical concentration of radioactive material present in this organ under conditions such that the organ received an assumed maximum permissible exposure over an indefinitely long period of time. 3. Comparison of radium and polonium toxicity with application of an acceptable maximal content of radium.

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This report gives the weekly status for the B, D, and F piles. Also given is the reactivity status at the end of the week for each pile. Process water control and pressure drop studies are discussed. Finally a brief discussion is given of the graphite expansion problem.