This memorandum discussed review of the data from tests using alum in the treatment of pile process water, and using activated silica as a coagulant aid during period of low water temperature, which shows that this method should be substituted for the present method of treating pile process water in all 100 Areas. It was recommended that the water treatment procedures and specifications attached to this memorandum be initiated as standard practice in all 100 Areas as soon as it is possible to make the necessary equipment modifications and installations.

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The Redox Plant operated at a 76.7% time efficiency (IAF basis) and averaged 3.16 tons of uranium per operating day during the month. During the period from July 4 through July 13, 38,000 gallons of 72% ANN from Tygon-lined storage tank SS-112 were used in aqueous salt solution make-ups with some emulsion difficulty and fission-product carry-over resulting. New ANN, from stainless-steel tanks, was used for the balance of the month. An extensive (thermally) hot 60% HNO{sub 3} cleanout was given to the IA, IB, 2D, 3D, 2A, and 3A columns and associated salt solution head tanks to prepare the solvent-extraction battery for operation using 90-day `cooled` uranium. Continuous cross-over oxidation to improve 2A Column waste losses, and employment of KOH (vice NaOH) in 2DS, ICU, and 2EU butt additions to minimize Na in 3EU, were begun concurrently on July 20. Aged (90-day) uranium in head-end treated feed batches, was started to the IA Column on July 21, with early data indicating adequate two-cycle decontamination for both uranium and plutonium.

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NpC and Pu{sub 2}O{sub 3} have been identified by x-ray diffraction. NpC is face-centered cubic, NaCl structure with a = 5.004 {+-} 0.005 A Pu{sub 2}O{sub 3} is isomorphous with the hexagonal ''A form'' for the rare earth sesquioxides with a = 3.840 {+-} 0.004 A; c = 5.957 {+-} 0.006 A and has essentially the same atomic parameters at La{sub 2}O{sub 3}. The lattice dimensions are smaller than predicted for pure Pu{sub 2}O{sub 3}, implying that the average oxidation number of plutonium is between (III) and (IV).

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Under conditions resulting from surface and underground detonations of atomic bombs, tests were conducted on Chemical Corps impregnated and unimpregnated protective clothing, Individual Protective Mask M9A1 with M11 Canister, Tank Collective Protector E26 and E22, and Protective Ointment M5. Both impregnated and unimpregnated clothing were capable of preventing contact between the skin and radioactive dusts. Unimpregnated clothing demonstrated better contanmination-decontamination characteristics, but the secondary radiation from all clothing was negligible. The protective cover was effective in preventing contamination of clothing. The M9A1 mask with M11 canister furnished complete protection against inhalation of radioactive dust. The flltering efficiencies of the E26 tank collective protectors were found to be very high, and no deficiencies were found in the unit. The filtering efficiencies of the E22 tank collective protectors were also high. Panels coated with M5 ointment were found to be much more highly contaminated than bare panels. (auth)

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The lack of control rod capacity in the reactors with nine rods is causing significant production losses. The present control system, which functioned satisfactorily at a 300 MW equilibrium power level, is unable to counteract the larger startup reactivity transient effects at the current high power levels. This lack of strength causes the power level to be restricted during startup. The control system is also not flexible enough to prevent outages for the discharge of temporary poison. (1) A method of obtaining the required supplementary control strength and flexibility has been conceived. (2) and equipment developed for this purpose. The purpose of this test. (3) was to demonstrate the operational feasibility of the special front and rear face equipment which was designed to permit the routine charging and discharging of poison slugs at selected process tubes during periods of reactor operation. This report presents the data, results and conclusions obtained from the trial use of this equipment.

Graphite burnout and chemical studies include: carbon dioxide - graphite reaction, controlled gas atmospheres, cyclotron irradiation, graphite - carbon dioxide - helium reaction kinetics. Physical properties studies include: hot test hole irradiation, surface studies, stored energy, physical expansion annealing. The experimental graphite program is discussed to include thermal conductivity and thermal expansion measurements. Also reported are: pile sampling, thermal conductivity of gases, irradiations in the MTR at Arco, in-pile controlled atmosphere program, heat generation in graphite, induction heater, mechanical properties programs and damage mechanism studies.

Studies of carbon dioxide fixation in green plants using the C{sup 14} isotope have shown that in very short times phosphoglyceric acid contains most of the radioactivity. The tracer is present almost entirely in the carboxyl group. The importance of organic phosphates in the subsequent metabolism of phosphoglyceric acid can be seen from the accompanying photographs.

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This report presents information pertaining to the life of the reduction bombs in both the RG and RMM Lines of the Plutonium Purification and Fabrication operations in the 234-5 Building. The expected average life to rupture of the RG Line Bomb of carbon steel subjected to an internal pressure of 450 psig is ten hours at 750 C. The expected average life of the RM Line bomb of V-36 alloy is more than 100,000 hours at 750 C under the same operating conditions. These expected average life values do not include any calculated factor of safety. Since they are average figures, some bombs could be expected to have shorter life to rupture. The BG Line bomb of carbon steel is definitely hazardous under the extreme service conditions of 450 psig and 750 C. If the use of carbon steel is to be continued it is recommended that the bombs be redesigned to reduce unit stresses.