Annual report for the U.S. Atomic Energy Commission Research Division describing work completed by programs at Nuclear Metals, Inc.

Report presenting tests of an airplane model equipped with missiles to investigate the capability of that combination to achieve satisfactory launching and jettisoning of the missiles. Information about pylon modifications, missiles in launch positions, missile trajectory, and missiles in jettison positions is provided.

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.

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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 …

Simultaneous reduction of coolant to several or all reactor tubes raises concern not only for the adequacy of protection in the individual process tube but also the reactor as a whole. In event of such flow reduction, the heat generation does not decrease until at least 1.4 seconds have elapsed following the accident. Thus, the water temperature from each tube will rise, and result in an increase in the bulk water temperature. If the increase in bulk water temperature is such that saturation temperature at the top of downcomer is reached, pressurization may occur at that point and exceed the maximum recommended working pressure limit (approximately 1 to 2 psig). The purpose of this report is to present experimental data on a series of tests which were made to simulate flow reductions to a K type process tube by simulated front header pressure decreases.

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.

During the outages of 9-28-57 and 10-14-57 a test was performed at KW-Reactor to evaluate conditions present during front nozzle replacement programs. The intent of the test was to prove that backflow from the rear crossheader would provide sufficient cooling to prevent slug damage under the following conditions: 1. The reactor has been shut-down at least eight hours. 2. The headers which supply rows of nozzles to be replaced are valved to the relief riser on the rear, and throttled to a header pressure of 26in. on the front. 3. No tubes may be open on the rear. 4. NO tubes closer than five lattice units on the front may be opened at the same time. 5. A maximum of five tubes per header may be open at one time. The test procedure used was to pick a high factor tube at goal exposure, obtain the above conditions, disconnect the front pigtail and remove the nozzle cap. The temperature of the backflow water was used with a previously calibrated thermometer, and the flow was measured with a calibrated bucket. One minute readings of temperature were obtained until the system attained equilibrium after which final conditions were obtained for rear inlet …

This is the monthly report for the Hanford Laboratories Operation. Metallurgy, reactor fuels, physics and instrumentation, reactor technology, chemistry, separation processes, biology, financial activities, employee relations, laboratories auxiliaries, radiation protection, operation research, inventions, visits, and personnel status are discussed. This report is for October 1957.

This document details activities of the irradiation processing department during the month of November 1957. A general summary is included at the start of the report, after which the report is divided int the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

A radiochemical study of fission and spallation products produced by bombardment of U{sup 233}, U{sup 235}, and U{sup 238} with 18-46 Mev helium ions has been made. As in the case of similar studies using isotopes of plutonium as targets, most of the reaction cross section is taken up by fission. Also, the pronounced increase of the total cross section for ({alpha},xn) reactions with increasing mass number of the target that was observed for plutonium targets is observed for uranium targets.

A method that can be used to produce milliliter amounts of tritiated water from tritium gas is described. Safety precautions are emphasized as part of the method, which involves oxidation of tritium gas over hot copper(II) oxide in a sealed glass system. (auth)

A survey of all the known literature on the subject is presented. This survey consists of four parts amd two appendices, namely: response of single- phase-fluid forced-convection heat transfer to a rapid change of velocity, response of single-phase-fluid forced-convection heat transfer to a rapid change of temperature of the surface or of the incoming fluid, response of single- phasefluid free-convection heat transfer to a rapid change of the surface temperature or of the heat flux through the surface, response time for boiling heat tramsfer to sudden increase in heat flux, or in temperature of the wall, summary of range and nature of published test results on the response to a sudden rapid rise in heat input which brings a surface immersed in water to a temperature above the boiling point, and symbols --nomenclature. (auth)

Abstract: The data presented herein, in the form of graphs, can be used to obtain the value of this energy.

Dispersion phenomena in packed beds in both axial and radial directions were studied to provide basic data for extraction-tower design. Nine different beds were used, involving regular and random arrangements of spheres, and random arrangements of Raschig rings and Intalox saddles. For one-phase flow a wide range of Reynolds numbers was used (5 to 2000), covering regions of laminar, transition, and turbulent flow. For the axial Peclet number, different constant values were found in the turbulent range and in the laminar range. The existence of a fairly sharp transition region was observed. Radial-dispersion results showed similar behavior. The axial Peclet number was found to vary inversely with bed porosity, while the radial Peclet number was almost proportional to porosity. For two-phase fiow, measurements were made up to the flooding point, which occurred at Reynolds numbers near 100. The axial Peclet number for both continuous and discontinuous phases is a function of the Reynolds numbers for the two individual phases. For each phase, the laminar value of the axial Peclet number obtained for one-phase flow is an upper limit. Values as low one- fifth of this limiting value were found at relatively large flow rates of the second phase. The radial …

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)

It is shown that the method of x-ray emission spectrometry can be extended advantageously to the determination of plutonium in solution, Since K and L x-ray emission from the elements of higher atomic number is not measurably influenced by valence state of the emitting atom or ion, this physical method is especially attractive for elements such as plutonium whose chemistry is intricate and whose chemical analysis is complicated by several valence states existing in solution. Nor is it affected by variations in isotopic content as is the widely used radiochemical assay for plutonium. With a total amount of plutonium between 0.4 and 0.8 mg the standard deviation of a single result is less than 1 per cent. For samples of diverse origin interferences are eliminated, usually by simple chemical pre-treatment or by separation procedures, to give a clean solution for analysis. On the other hand, for large numbers of samples with a comparable matrix, it is worthwhile to devise calibration standards so that such samples can be analyzed directly. (auth)

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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.)

The first phase of a program aimed toward the development of materials and a core-subassembly design for the second core of the Fermi Reactor is outlined. The ground rules established by APDA for the study were based upon the performance requirements of the reactor plant with some modification to permit hlgher power generation and upon a value of Pu produced of about per g. Consideratlons of various factors led to the selection of the dispersion or cermet fuel as havlng the most potential for the Core II application. The fuel selected was a 30 vol. % dispersion of UO/sub 2/ in U--10 wt. % Mo or gamma- phasetype alloy, zirconium clad, in a flat-plate-subassembly design. The plant economics for subassembly designs of the fuel systems were evaluated at a core power level of 616 Mw. (W.D.M.)

The oxidation of Hg in HNC/sub 3/ was investigated. An empirical rate law, oxidation rates, and Hg species in solution were determined. A reaction mechanism based on the presence of nitrous acid can be interpreted in terms of the rate expression derived. (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 …

Tests have been run to determine in a preliminary fashion whether ultrasonic vibration would be effective in removing mixed radioactive deposits from the inside surface of steel pipes in a heat exchanger. Different frequencies (20 KC/S, l000 KC/S) have been used at the maximum power levels conveniently attainable. Different liquids were compared for cleaning effectiveness, with and without ultrasonics. Mild stirring of water bath at room temperature produced virtually no cleaning effect on the samples. Ultrasonics in water, at room temperature, gave 50% to 80% cleaning (as defined by gamma ray count) in 15 minutes or less. Certain chemical solutions gave moderate cleaning results without ultrasonics; but the effectiveness of these solutions was greatly enhanced by the addition of ultrasonics. It was found, as expected, that the effectiveness of the sound wave depended rather critically on the method of coupling to the work. (auth)