The results of the work on activities is the Ma-- Pb--Bi alloys, solubility of Fe--Ni alloys in Pb, and phase distribution in Fe--Ni-- Pb and Fe-- Ni-- Pb--C systems are briefly summarized. (For preceding period see AECU3385.) (J.E.D.)

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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At an Octcber, 1957 meeting between USAEC, AECL, and Bettis personnel, the theoretical aspects of the radiation effects on the gamma red and alpha + gamma /sub 2/ transformation in U-Nb alloys were discussed. A theoretical model is presented which involves the annihilation of nuclei of the new phase by the action of displacement spikes. (W.D.M.)

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The equilibrium constants for oxidation reactions occurring in molten U alloys are estimated from thermodynamic principles. Preliminary qualitative information was provided on: the relative ability of various elements to deoxidize U, and the relative stability of the oxide formed as a result. The latter will guide in the selection of oxides as possible crucible materials. Ideas were obtained on possible purification of U by melting. (M.H.R.)

The change in critical concentration due to axial holes of various diameters in a right circular cylinder containing D/sub 2/O and pure U/sup 233/ or U/sup 235/ is discussed. This geometry is intended to represent an aqueous homogeneous reactor with a central void due to rotating flow of the fluid through the core. The critical equations and results of calculations are given. (M.H.R.)

Quantitative criteria for judging the performance of a nuclear counting channel are discussed. Several procedures for evaluating the performance of the counting channels were combined with statistical tests of significance into one method or test. Statistical purity checks, comparison of actual and theoretical standard deviations, the Fisher variance test, and a chi-square test are described. (M.C.G.)

Record highs were set for Pu output in separations plants and for amount of U processed in Purex. UO{sub 3} production and shipments exceeded schedules. Fabrication of 200 and 250 Model assemblies is reported. Unfabricated Pu production was 8.5% short. Nitric acid recovery in Purex and Redox is reported. Prototype anion exchange system for Pu was tested in Purex. Hinged agitator arms with shear pin feature was installed in UO{sub 3} plant H calciner. Operation of continuous type Task I, II facility improved. DBBP is considered for Recuplex. Methods for Pu in product solutions agreed to within 0. 10%. Purex recycle dock shelter is complete. Other projects are reported.

The feasibility of the coated metal crucible as a container for eutectic Al--Si alloy was proven by test. Small enamel-coated east-iron pets have successfully withstood Al-- Si alloys and an oxidizing atmosphere for a period of 3 months at 725 deg C. A similarly coated east-iron crucible containing 450 pounds of eutectic Al--Si alloy was successfully tested for 144 days in a jacketing operation conducted at 595 deg to 650 deg C. Under the same conditions, the normal service life of clay-bonded graphite and silicon carbide crucibles rarely exceeds 45 days. The coating material for the iron crucible is a commercially available enamel capa ble of withstanding temperatures up to 790 deg C. lt is readily applied to the surface of a variety of ferrous metals and alloys; however, best results are obtained with alloys low in chromium and nickel which also have a low thermal expansion coefficient. (auth)

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 …

E-Metal production is scheduled to start through the UO{sub 3} Plant in July of 1958. E-Metal is defined in HW-46138 as uranium metal enriched with U-235 to a level selected to be always-safe for non-metallic uranium forms, i.e. for compounds encountered during solvent extraction or calcination. Currently E-metal as selected contains 0.94% U-235 prior to irradiation. Planning of a segregation facility requires that the mixing of E-Metal with normal uranium be minimized, thereby preventing costly downgrading. Segregation of E-Metal through existing facilities would require extensive cleanout and flushing. Production scheduling with present demonstrated capacity would make this method impossible. The Redox Plant will produce E-Metal on an intermittent basis. It is expected that normal operating production of E-Metal through the Redox Plant will be quantities of 100 to 200 tons. Production through the UO{sub 3} Plant will follow on this same intermittent basis. During the first two quarters of FY `59 the UO{sub 3} Plant production of E-Metal is forecast at not greater than 100 tons per quarter. Following this initial period the E-Metal production is forecast to run 135 to 200 tons per quarter for the next three to four years. It is the purpose of this document to …

The gas lift pump has not been considered here as a prinme mover for circulating coolant through a primary circuit, in view of the complexity which would arise in designing such a pump to overcome the head losses associated with the secondary large volumetric flow rates. The purpose of this investigation was merely to make a preliminary study of the general character of a heavy liquid metal gas-lift, to compare its operation with that of water, and to obtain some idea of the relationship of efficiency to flow rate. (A.C.)

An investigation of the inelastic and elastic reactions between high- energy neutrons nnd He nuclei was conducted with a cloud chamber filled with He and operating in a pulsed magnetic field of 21,700 gauss. Neutrons produced by bombardment of a 1/2-in. LiD target with 340-Mev protons in the 184-in. synchrocyclotron were collimated and passed through the 22-inch expansion cloud chamber, which was filled with He gas to a total pressure of 89.8 cm Hg. Exclusive of meson-producing reactions, the possible reactions are: Inelastic, He/ sup 4/(n,pn)t, He/sup 4/(n,d)t, He/sup 4/(n,2np)d, He/sup 4/(n, dn)d, He/sup 4/ (n,2n2p) n, He/sup 4/(n, 2n) He/s up 3/; and Elastic, He/sup 4/(n,n)He/sup 4/. The total number of events, for incident neutrons above 160 Mev, was normalized to the interpolated n-He/sup 4/ total cross section at 300 Mev, and absolute cross sections for the various processes were established. Energy and angular distributions of the reaction products were compared with available theoretical predictions and other experiments. A few cases of meson production were noted. (auth)

As a result of the partial meltdown which occurred in EBR-1 on November 29, 1955, it was necessary to remove the core assembly from the reactor and to separate the enriched fuel section from upper and lower unenriched blanket sections. A temporary cave was constructed on top of the reactor in order to remove the core assembly, and at this time about one-fourth of the fuel elements were removed. In order to perform further disassembly operations under less hazardous conditions, the core assembly was shipped from the Idaho Division of Argonne National Laboratory, at the National Reactor Testing Station, to the Lemont, Illinois, site of the Laborntory, where disassembly was completed in a protective atmosphere. It was found that approximately 40 to 50% of the core had melted and reached temperatures ranging between approximately 850 and 1400 deg C, and that the molten portion had separated into three clearly defined zones characterized by different porosities. Densities of the zones ranged from 2.5 to 15.4 gm. cm/sup 3/, depending upon the degree of porosity. It was also found that molten fuel alloy had traveled upwnrd 5 inches and downward 3 inches between the blanket rods. Chemical and mass spectrographic analyses indicated …

Epinephrine injection has been shown to produce a two and three fold increase of the higher Sf classes of serum lipoproteins in the rabbit. The previously observed elevation of serum lipids was confirmed. The hyperlipoproteinemia following epinephrine injection appears about the same time as in certain conditions of stress. (auth)

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The slowing-down distribution, to thermal energy, of neutrons from a U/ sup 235/ fission source in an infinite H/sub 2/O medium up to 160 cm was determined from experimental data. The Fourier transform of this distribution and the In resonance distribution, which are the nonleakage probabilities for bare reactors, were also determined. (auth)

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Data were obtained to evaluate the attenuation of photons, emitted from a fallout field, due to the surface roughness of the terrain. A study was made to determine the effect of the shot tower on the fallout material. Particles for comparison were collected from two detonations of equal scaled height, one tower supported and the other balloon supported. Data on time-dependent phenomena were recorded, as were physical characteristics of the fallout material. The use of small balloons as instrument platforms and a new fallout collector were evaluated for field use. No conclusions or recommendations can be made at this time. (auth)

Data were obtained to evaluate the attenuation of photons, emitted from a fallout field, due to the surface roughness of the terrain. A study was made to determine the effect of the shot tower on the fallout material. Particles for comparison were collected from two detonations of equal scaled height, one tower supported and the other balloon supported. Data on time-dependent phenomena were recorded, as were physical characteristics of the fallout material. The use of small balloons as instrument platforms and a new fallout collector were evaluated for field use. No conclusions or recommendations can be made at this time.

Data are presented for the rates of formation of din-butyl phosphate (DBP) from tri-n-butyl phosphate. The effects of DBP on the extraction of zirconium from nitric acid and uranyl nitrate are reported. (auth)

The hydrogenic (unscreened coulomb) free-free gaunt factors are computed for a wide range of initial energies and photon frequencies. In addition, an average over initial energies with the Maxwell-Boltzmann distribution is performed to give the temperatureaveraged gaunt factors for use in opacity calculations. These are presented as functions of Z/sup 2//kT and h nu /kT. The relation between these gaunt factors and the rate of bremsstrahlung energy production is given, as is the total energy emitted as a function of Z/sup 2//kT. (auth)

This document details activities of the Fuels Preparation Department during the month of October 1957.