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The purpose of this document is to present in graphical form a current picture of the quality of the Hanford plutonium product.

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The Turco 4501 process is recommended for the decontamination of the PRFR pilot leaching plant equipment. The caustic-tartrate-nitric acid process is recommended for the decontamination of the cell and the equipment exterior. (auth)

Corrosion tests were made on nickel-base brazing alloys containing boron snd silicon in fused fluoride fuels, liquid metals, nnd oxidizing atmospheres. Impoverished regions, after the tests, contained, approximately one third the original amount of boron and silicon that was present before the tests. (A.C.)

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The nil-ductility-transitaion (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness locations from material used in the ipper closure head of the reactor vessel yielded NDT temperatures of 0 to 20 deg F which correspond to Charpy-V-notch impact energies of 11 to 19 ft-lb. Testing of as-received material used in the lower closure head indicated that the NDT temperature was 50 deg F which was equivalent to an average CharpyV-notch impact energy of 12 ft-lb. After normalizing and stress-relieving thin material, in order to more closely approximate the final ccndition of the reactor vessel, NDT was reduced to less than 10 deg F. (auth)

The thenoyltrifluoroacetone (TTA) extraction method has been investigated for the determination of microgram concentrations of thorium in uranium ores and concertrates. The tolerance limits for eighteen elements commonly found in uranium ore concentrates were established. The effect of phosphate on estraction of thorium was studied. Cobalt, copper, tin, and bismuth were found to seriously interfere with the Thoron method for the determination of thorium after a TTA extraction. A TTA extraction method is described for the separation of thorium and uranium from the interfering ions, employing preliminary acid sulfide and ammonium hydroxide separations. The method is rapid, and results obtained compare favorably with results obtained with other procedures. (auth)

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The casting procedures, mechanical working characteristics, composite fuel plate fabrication, and fuel element assembly methods for a nominal 48 wt.% U- 3 wt.% Si -AP alloy are examined. It was found that localized clad thinning, resulting from dogboning'' of the fuel alloy, is essentially eliminated in composite Plates when this alloy is used in combination with 5154 Al frames and 1100 Al covers. However, fuel component dimensions are difficult to maintain within commonly accepted tolersnces in the brazing prccess because of the marked differences in the thermal expansion of the fuel alloy and the containment materials. The mechanical properties, irradiation studies, corrosfon testing, pneumatic pressure testing, and chemical reprocessing of the Si-modified alloy are also discussed. (auth)

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In accordance with the agreement in a meeting with Aerojet-General Nucleonics representatives, certain information is presented for use in planning the first DR Gas Loop test run. Included are the following: estimates of test section power prediction uncertainty and variation during run; estimates of limiting test section design powers and {Delta}P`s, presented as variables versus maximum loop flow as a parameter; spatial relation between in-pile tube and reactor surroundings; and a representative relative flux traverse in the sample space. The user of this information is cautioned to study the discussion to fully understand the significance of what is presented.

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In the preoperational checkout of the APPR-1 it became apparent that the control rod acceleration after scram was lower than expected. It was expected that the control rod acceleration after scram would be 0.750 g(1) where g is the acceleration of gravity. However, measurements made at Ft. Belvoir indicated an acceleration of 0.4 g. The effect of this reduced acceleration on the safety of the APPR1 is reported in this memo. In the operation of the APPR1 the most dangerous condition exists at cold startup. Therefore the behavior of the APPR-1 in a startup accident with a rod acceleration of 0.4 g after scram is considered. Analysis of the most adverse startup accident in the APPR-1 indicated that at the 15 Mw level scram the reactor is on a 33 ms. period. Rod insertion begins after a 50 ms. instrument delay, at which time the power is 80 Mw. The maximum power reached with a rod acceleration of 0.4 g is 96.5 Mw. The total energy released is about 5.8 a 10/sup 3/ Btu which is far below the 8 x 10/sup 4/ Btu which would result in melting at the center line of the fuel element (and probable core …

Tests have been made to study the effects of lowering process water pH from pH 7.7 to the range pH 6.2--7.3; of reducing the amount of sodium dichromate inhibitor added to the water; and of eliminating the filtration step in the water treatment process. The results on the pH testing showed that reducing the pH of the cooling water would reduce aluminum corrosion rates. The plant specification has been changed to lower process water pH from 7.7 to 7.3 and plant scale testing of pH 7.0 water is in progress. Reducing the dichromate concentration in the water from 2 to 0.2 ppm had no deleterious effects on the aluminium pile components but might cause pitting of the carbon steel pile effluent lines. The use of unfiltered water is technically feasible from the stand-points of corrosion and film formation but probably would cause a sizable increase in the radioactivity of the pile effluent water. 6 figs., 5 tabs.

A fall-out sample collector was designed and tested for use in collecting samples at the soil surface. The sampler consists of artificial grass and a stainless steel pot. Results are included from preliminary studies on the scavenging properties of artificial grass. The effects of relative humidity, rain, and wind velocity on the efficiency of scavenging devices were investigated. A comparison was made of Sr/sup 90/ fall-out data from samples collected on gummed film and surface soil samples from various locations. Preliminary experiments were performed for the evaluation of devices used in determining air concentration of radioactive fall-out or other particulate matter. (For preceding period see AECU-3435.) (C.H.)

An endurance test was made to determine the reliability of the Mark ll control rod drive. The control rod drive unit completed 1300 scrams and the results are presented. (W.L.H.)

The basic information about the path of carbon in photosynthesis is reviewed together with the methods that were used to discover it. This has led to the knowledge of what is required of the photochemical reaction in the form of chemical species. Attention is then directed to the structure of the photochemical apparatus itself insofar as it is viewable by electron microscopy, and some principoles of ordered structure are devised for the types of molecules to be found in the chloroplasts. From the combination of these, a structure for the grana lamella is suggested and a mode of function proposed. Experimental test for this mode of function is underway; one method is to examine photoproduced unpaired electrons. This is discussed.

Adoption of a two-cycle solvent extraction process at Purex, in place of the present three-cycle process, offers great potentialities for reduction of manufacturing costs, improved product and by product recovery and increased capacity. This report deals with the engineering feasibility of converting Purex for two-cycle operation.

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In a previous study it was determined experimentally that heat deterioration, or burnout, of the shield masonite is more severe than radiation damage under existing and proposed operating conditions. Higher shield temperatures, which are expected to result from increased power levels, fringe enrichment, and higher graphite temperatures, will markedly increase the rate at which the masonite burns out. The laminated iron-masonite biological shield will lose, as a result of burnout, the hydrogen and oxygen necessary to attenuate and moderate neutrons. The purpose of this production test has been to obtain experimental data from which future shield leakage rates could be estimated. The attenuation data reported here were obtained in the DR pile bulk shield facility from experiments using various void spacings to simulate burnout conditions. From these data it was hoped to determine (1) the resultant attenuation properties of the shields, and (2) the exposure rates due to radiation penetrating the shield.