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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.

Activities for the month of February are as follows: (1) calculations of reactivity and temperature limits; (2) calculations of operating levels of D pile if reduced in size; (3) symposium on power coefficients; (4) test of new vertical (safety) rods; (4) metal quality studies; (5) status of process tube ionization chamber failures; (6) reactivity balance of each of operating piles; (7) graphite testing; (8) water activity calculations; (9) pile shielding; (10) radioactivity of titanium; and (11) critical mass experiments.

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.

Experimental results on the adsorption of U from solutions by activated C indicate that low pH values reduce the adsorption and that a marked change occurs in the adsorption of U(VI) at pH2. Under a given set of conditions the adsorption of U follows a typical Freundlich isotherm. The particle size of the charcoal affects the rate of adsorption but not the amount of U adsorbed at equilibrium. The temperature coefficient of adsorption is negligible, and the adsorption of U from uranyl solutions is a reversible process. (BJH)

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The meetings divided into two parts, with reviews of work being done in radiobiology at the University of California by various members of their staff as part one, and, as part two, a meeting conducted by Dr. Shields Warren for Laboratory Directors and their representatives. For the most part papers which were reviewed were summarized material which has appeared in the literature and gave progress to date. Since the purpose of the meeting itself was more for the informal directors meetings, results of the latter are here abstracted.

This progress report discusses activities for the P Division for the month of May 1949. The nominal operating level for both B and F Piles was 275 megawatts (MW) throughout the month except for outages listed under Area Activities. The D Pile operated at 275 MW until May 23 when the nominal level was raised to 290 MW in the first step of the program covered in Production Test No. 105-260-P to evaluate the feasibility of operating piles at higher power levels. A total of 44 tons of metal, at an average concentration of 285 megawatt days/ton (MWD/ton), was discharged from the piles during the month. Considerable difficulty was experienced during the month with stuck tubes containing Class IV (alpha-rolled, triple-dipped, randomly transformed) metal. A total of nine tubes with concentrations in the range of 320--370 MV/ton was encountered. As a result of these difficulties with the Class IV material, future discharges of this type metal will be limited to concentrations in the range 300--320 MWD. Approximately one ton of Class V (alpha-rolled, triple-dipped, completely transformed) metal was discharged at a concentration of 368 MV/ton for test purposes. Inspection of this material indicated that all the slugs were in satisfactory …

A comparison of the decay constants of Be{sup 7} in beryllium oxide and in beryllium fluoride has given {lambda}{sub BeO}-{lambda}{sub BeF{sub 2}} = (+1.375 {+-} 0.053)10{sup -3}{lambda}{sub BeO} thus showing a definite effect of the chemical binding on the radioactive decay constant.

The available information on the ionic and radiochemical composition of current and aged bismuth phosphate process wastes is tabulated here for the convenience of those concerned with metal recovery. In addition to its application in the design of research and development experiments, the compilation may serve to suggest specific needs for additional analytical data. For convenience in chemical calculation, molar compositions have been calculated for the ionic constituents based on the g/1 values usually reported. The dates of radiochemical analyses required for decay calculations should be available from the Analytical Sections at ORNL and HW.

At the spring, 1949, meeting of the National Academy of Sciences(l) a preliminary account was given of some observations of mesons produced by the 335 Mev x-ray beam from the Berkeley synchrotron. The present paper is a progress report of this work; no claim is made for completeness, but sufficient new data are available to make publication at this time worth while, especially since some of the numerical results given in the earlier report require revision. The x-ray beam, produced by the impact of 335 Mev electrons on a 20 mil thick platinum target, has a width at half maximum of 0.0135 radian (about 1 inch at 6 feet from the target). In all but the earliest experiments the beam was further defined by a 1 inch hole in a lead block, then passed through a piece of carbon which served as the meson source. The x-ray intensity at one meter from the target was about 3500 r per hour (measured behind 1/8 inch of lead) under the best running conditions; the average was about half this. The actual exposures at the carbon meson source (6 feet from the target) ranged from 500 to 2000 r in the later runs. …

A design is proposed for a removable drainage grill and trap for floor drains in radioactive risk areas. One simple element provides free liquid run off, an air and fume barrier, and ready access for cleaning or replacement in event of contamination. Application may be made to existing and future untrapped drains.

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The test unit is to simulate the conditions existing in the ``active``section of a pile process tube. This section is loaded with 64 slugs each of length equal to 4.3767 inches, giving an overall active length of 23.34 feet. The figure of 4.3767 inches is the overall length of the aluminum can, rather than that of the slug proper. The calculations tabulated on the accompanying data sheet are representative of the conditions of operation of the ``maximum performance tube`` in the pile. The resistance of a heater element with the specified wall thickness is such as to give a total heating of 552 Kw (corresponding to an 800 mw operating level) with a current of 13,000 amperes flowing through the tube. The heating distribution is a sine curve with a maximum heating of 33.56 Kw/ft. at the center. No attempt will be made to simulate the heating distribution in the aluminum end cap.

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This report details events of importance reported by the Hanford Operations Office for the week ending April 13, 1949.

This report details events of importance reported by the Hanford Operations Office for the week ending July 13, 1949.

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