This is the monthly report of the Hanford Laboratories Operation, March, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

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The purpose of this work was to investigate the possibilities of producing a plastic bonded explosive having greater mechanical strength than that of presently existing plastic bonded explosives. This interim report details activities and progress through July 15, 1957.

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ABS>A hypothetical reactor core is presented in which right cylindrical fuel regions sre positioned at the core corners of equilateral, space-filling, parallelograms. The average gamma heating rate density in each of a set of concentric annular regions, centered on a fuel cylinder, is presented for three different fuel cylinder separation distances. The fuel cylinder radius, fuel composition, and moderator composition are held constant. The calculation was done using the Monte Carlo method. (auth)

The difference in rates of reaction of isotopic molecules may be utilized to produce appreciable isotope enrichments. When a competitive irreversible isotopic reaction is carried out to a high extent of completion, the residual unconverted substrate becomes exponentlally enriched in the heavier isotope. In deuterium systems, a substantial function of the D inventory is retained in the enriched residual substrate, so that conversion of the depleted product is unnecessary. For isotopes of heavier elements such as C/sup 13/, N/ sup 15/, and O/sup 18/ the retention is low, so that product conversion and recycling is desirable unless the starting material is of negligible value. Experiments are described in which enrichments of C/sup 13/ have been obtained using the reaction rate principle in dehydration of formic acid and hydrolysis of urea. Procedures are given for the preparation of decimolar barium carbonate at the level of 1.6% C/sup 13/, and molar barium carbonate at the 1.4% level starting with commercial materials. (J.R.D.)

This report has been prepared in answer to the request from the AEC contained in the letter of October 1, 1957, from A. T. Gifford, HOO to A. B. Greninger. As requested, the report is of a summary nature and a more complete discussion of many of the points considered will be found in the references listed. The report is directed primarily at C reactor but some discussion of the other reactors is also included. A description of the proposed utilization of I E slugs in C reactor together with the associated power increase schedule is presented below. The reasons for changing to the I E element are presented together with a comparison of solid and I E slugs in the C reactor. The changes being made in C reactor under CG 600 are described. The operational characteristics of the C reactor using solid and I E elements are compared and finally the nuclear safety status of all of the Hanford reactors assuming I E loadings is reviewed.

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The problem of feeding a pulsed megnetron into a high Q (greater than 10,000) circuit was solved by incorporating a high power ferrite isolator into the appropriate microwave circuit. The PACE analogde computer has been programmed, and curves of particles displacement and velocity have been computed for field strengths from 50 to 500 kv/ cm and injection velocities ranging from 0.24 to 0.40c. Analysis of the slow-wave, dielectric, higher order mode resonator included the computation of the TE mode design curves, plots of the mode patterns, and the preparation of a five mm experiment using the rebatron. Detailed theoretical investigations of the general behavior of the Harmodotron were made. The TM and TE modes of metal and dielectric cavities were compared. Analog circuits were examined to determine the limiting efficiency for frequency conversions in crystal multipliers. A mount in which the Wollaston wire was etched directly in the mount, was designed for the bolometer detector. (For preceding period see AECU-3594.) (J.S.R.)

Work on the present relativistic electron bunching accelerator (S-band rebatron) is concerned with improving the electron bunching, current and beam focusing, and the design of a portable prototype system. Most of the parts for this new machine were fabricated and tested and the construction initiated. A photograph showing the present stage of construction is given. Since an S-band rebatron cannot be scaled directly to X-band, a lower voltage Xband rebatron, followed by a short section of a linear accelerator could solve the problera. An Electronics Associates analog computer was received and is being programmed to explore the design problems. The numerical work of evaluating the TM and TE modes of teflon dielectric cavities is largely completed. New ideas and further modifications are being tried in Si crystal harmonic multipliers for use as sources for testing components. The new klystrons now being used permit driving the crystals harder, and hence improve the harmonic power. (For preceding period see AECU-3535.) (M.H.R.)

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Tensile properties amd impact strengths were determined for iodide Zr, sponge Zr, and alloys based on both grades of metal, containing nominally 1.5% M. Sheet specimens, welded and unwelded, were tested. Tensile properties were established at room temperature and 300 deg C. Impact strength values were measured at --100 deg , R.T., 100 deg , 200 deg , and 300 deg C. These (alpha) materials generally exhibited a lack of heat treatability, litile or no deterioration of properties due to welding, and essentially no indication of impact transition temperature. Tensile strength and impact behavior were established for alloys based on iodide zirconium containing 15% Nb, 15% Nb + 2% Pd, 15% Nb + 2% Pt, 15% Nb + 1% Fe, and a binary sponge zirconium + 15% Hb alloy. High strength levels could be established by proper heat treatment. The presence of Pd, Ft, or Fe seemed to delay the formation of the embrittiing agent as determined by hardness and resistivity vs time of anneal curves for these alloys. uth)

Temperature distributions, irradiation effects, stacking arrangements, voidage, and economics for the borated-graphite shield of the PRDC reactor were investigated. Of the shield systems considered, four are reported here. System 1 contalns 30 in. of 1% borated graphite, with either ordinary graphite or a cement as a filler for the remaindcr of the volume. The maximum temperature at the flex plates in this system was calculated to be 5OO deg F. Systems 2 and 3 consist of 2 in. of 5% borated graphite near the core vessel and 1/2 in. of Boral at the primary-shield tank. A filler material of carbon blocks is used in System 2 and graphite in System 3. The calculated maximum temperatures were 700 deg F and 35O deg F, respectively. System 4 consists of a laminated structure of Boral and graphite near the primary-shield tank and carbon-block filler. It was calculated to have a maximum temperature of 600 deg F at the flex plates. The maximum temperature at the flex plates recommended by APDA is 500 deg F. Energy storage and radiation damage were found to be within permissible limits in all four systems. However, these conclusions are based on experimental data from the Hanford reactor …

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During the course of the ZPE-2 experimental program additional measurements were performed under the Alco Products Research and Development program. Included in this program were the evaluation of various absorber section compositions and reactivity studies designed to facilitate analytical techniques. The results of these measurements are presented. (auth)

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This document contains information on the progress of work for the Hanford facility for the month of February 1957. Included are personnel reports, research and development of various operations, radiation protection and invention reports.

This is the monthly report for the Hanford Laboratories Operation, May, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This is the monthly report for the Hanford Laboratories Operation, September, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

It is expected that after the Homogeneous Reactor Test has operated at high power, some maintenance operations will require flooding the reactor cell. Minimum temperatures for preventing peroxide precipitation from the fuel solution during flooding are plotted. (D.E.B.)

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Experimental data obtained from the simulating air flow rig indicated that though the fluid entering the fuel elements amd control rods from the plenum chamber follows a rather random behavior, there is, however, a fairly consistent distributional pattern. Thus, fuel elements located equidistant from the core center may require different orifice diameters to meet a given flow requirement. This, in fact, is apparent from the final orifice diameter schedule which was recommended. Control of flow into the control rods was accomplished by restricting the flow into the fuel elements, thus allowing more fluid to enter the reds. Orificing or direct forms of flow regulation were not used on the control rods since their geometry was not conducive to installation of control means, and also because of the satisfactory results obtained with resort to flow control devices. The effect of the orifice schedule on the coolant flow distribution in the core is shown. These curves are based on the average of V/V/ sub avg/ values determined from experimental data for families of fuel elements and control rods located at specific core radii. It should be noted that the final recommended orifice schedule is an attempt to further refine the nearly satisfactory …