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A study has been made of the elution behavior of curium(III), americium(III), plutonium(III), actinium(III), plutonium(IV), neptunium(IV), uraniuM(IV), thorium(IV), neptunium(V), plutonium (VI), uranium (VI), lanthanum(III), cerium(III), europium(III), ytterbium(III), ytterium(III), strontium(II), barium(II), radium(II), cesium(I) with 3.2 M, 6.2 M, 9.3 M, and 12.2 M HCl solutions from Dowex-50 cation exchange resin columns. These elutions show that in high concentrations of hydrochloric acid the actinides form complex ions with chloride ion to a much greater extent than the lanthanides. The strengths of the tripositive actinide complex ions apparently go in the order plutonium > americium> curium, although their ionic radii also decrease in this same order. To explain these results, a partial covalent character may be ascribed to the bonding in the transuranium complex ions. It is shown that a reasonable structure for such covalent bonding involves hybridization of the 5f orbitals in the actinide elements.

The amount of Ac/sup 227/ per curie of Ra/sup 226/ was calculated for various values of neutron flux and various Irradiation times. The amount of Th/ sup 228/ produced per curie of Ra/sup 226/ and the percentage of Ac/sup 227/ converted to Th/sup 228/ relative to the total amount of Ac/sup 227/ produced were also calculated. (W.D.M.)

Progress is reported on the following projects: Th alloy development, mechanical properties of Th, tensile properties and preferred orientation of Th, triple-dip slug canning, texture studies, fundumental studies of alloying, static cerrosion tests with low melting point alloys, dynamic corrosion testing of fluoride materials, mass transfer, structures of liquid Pb and liquid Bi, fabrication of tubular laminates for fuel elements, creep of Th, cone-arc welding, Homogeneous Reactor Experiment metallurgy, a low-temperature specimen holder for use with the highangle x-ray spectrometers, metallography of Zr and its alloys, automatic polishing machine, a fuel element manufacturing process for the direct-cycle aircraft reactor, and fabrication of fuel and control rod elements for the MTR. (L.T.W.)

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Citrilline has been isolated and identified from extracts of Nostoc muscorum. All members of the Cyanophyceae hitherto investigated show a relatively large amount of the CO fixed during photosynthesis in citrulline (ranging as high as 20% in Nostoc) when compared to the trace amounts found in the Chlorophyceae. Nostoc also has the ability to fix C{sup 14} in citrulline during dark fixation, but at a rate slower than in light. As no free urea or arginine was found in Nostoc, it is likely that citrulline is functioning in reactions other than those leading to arginine and urea synthesis. Other possible functions for citrulline are briefly discussed.

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Generally low attack rates were displayed by specimens of type 347 stainless steel, titanium RC-55, and nket pe 347 stainless steel suffered more severe attack dut to erosive action by the slurry. Specimens SA-212-B carbon steel displayed attack rates of 230 to 300 mpy. (auth)

The fundamentals for the stress analysis of conical shells by use of the classical small-deflection theory have been presented in various texts, but before the development of the high-speed computing machines it was not feasible to present the anaylsis in a convenient and usable form. With the aid of these high-speed machines, all necessary functions can be evaluated by the fundamental analyst and tabulated in a convenient form for use by tbs design engineer. It in the intent of this report to bridge the gap between theory and design. Parts I and II are sufficient for the analysis of a specific conical shell. Part III consists of several illustrative examples and the necessary additional equations for ''connecting'' a cylinder or a flat circular plaa to either end of a cone. These equations pertain to the ''funnel'' and the ''flower pot'' problems, respectively. Part IV gives the derivation of the conical-shell formulas, and part V consists of tables of values of the Schleicher functions and their first derivaiisves, which form the core for the values of almost all the other required functions but do not apply directly in the stress analysis of conical shells. (auth)

Materials of construction were evaluated for use in critical areas of head-end processes for the aqueous reprocessing of spent nuclear fuel elements. The SulfexThorex, Darex-Thorex, Darex, Zirflex, and Zircex processes were considered. The effect of varying heat treatments on the resistance of the materials was also evaluated. Dissolution of unirradiated fuel pins was carried out in vessels of promising materials. The corrosion rate of Ni-o-nel was about 5 mils per month during actual fuel-pin dissolution by the Sulfex-Thorex process. Stabilization and heat treatment are necessary to prevent intergranular attack at welds. Carpenter 20 Cb is subject to stress-corrosion cracking by the Sulfex decladding solution and Illium R behaves similarly to Ni-o-nel in Thorex solutions. Titanium shows promise as a construction material for a Darex-Thorex dissolver. However, several questions remain concerning a vapor-phase attack observed around certain weldments. Carpenter 20 Cb, Ni-o-nel, and Types 309 and 309S Cb stainless steel appeared worthy of further study for the Zirflex dissolver. Preliminary evaluations show that at least Ni-o-nel and Carpenter 20 Cb should be studied further as possible construction materials for a single vessel for Zirflex and Sulfex-Thorex processes. Illium R, Hastellcy C, and nickel were not attacked by hydrcchlorination conditions of the …

Objective of this test is to authorize irradiation of alloyed, low hydrogen dingot uranium fuel elements on a pilot scale, and to monitor their performance. Initially, 25 tons per month of alloyed, low hydrogen dingot material will be charged for two months. Measured charges will be loaded with the initial 25 tons to monitor the stability of this material. Following a two-month delay in the monitor charging, and if the dingot meets all specifications, routine charging of quantities up to 60 tons/ month may proceed for six months and, assuming continued favorable performance, up to 150 tons/month may be accepted to complete large scale evaluation of dingot uranium, and on a continuing basis thereafter.

A solid-state bonding technique involving the use of gas pressure at elevated temperatures was investigated for the preparation of compartmented Zircaloy-clad flat-plate uranium dioxide fuel elements. These investigations involved development of methods for the surface preparation and assembly of fuel- element components for bonding, determination of optimum bonding parameters, development of barrier coatings for uranium dioxide to prevent reaction with Zircaloy, and extensive testing and evaluation of the bonded fuel elements. During the course of this work, the process was continually modified and refined in an effort to improve the quality of the bonded element and decrease the cost of fabrication. The surface-preparation studies indicated that satisfactory bonding could be obtained consistently with both machined and belt-abraded components. Belt abrasion is more economical and was used as the standard technique in the development phases of the program. Initially the elements were assembled into a stainless steel or Ti-Namel envelope which was evacuated and sealed prior to bonding. Later studies showed that the quality of bonded elements could be improved and process costs decreased by edge welding the Zircaloy components to form a gastight assembly that was then bonded without use of a protective envelope. Further cost reductions were incorporated into …

A 3-inch-diameter flame tower for the conversion of uranosic oxide to uranium hexafluoride with elemental fluorine was tested for possible use in the fluorination step of the present uranium recovery process. The oxide was fed from a hopper to the tower by a screw feeder. The fluorine and the oxide entered at the top and flowed concurrently down through the tower. The unreacted or partially reacted oxide was collected in an ash receiver at the bottom. Fine solid particles were removed from the gas stream by an electrostatic precipitator and a tune-type filter. The uranium hexafluoride was collected in cold traps. Twenty-five experimental runs were conducted with average oxide feed rates from 3.73 to 19.38 lb/hr. The average fluorine flow rates were from 7.5% below to 44% above the stoichiometric amount of fluorine required. The best operating conditions were at a feed rate of 15 lb of oxide per hour with a minimum fluorine excess of 75% 110.6 lb of fluorine per hr). The material collected in the tower ash receiver represented between 6.0 and 10.0 percent of the total amount of uranium fed during the run. The ash, combined with an equal weight of oxide, can be fed back …

Activities are discussed for research in design investigations, and materials development and testing conducted in connection with the development of the EGCR. The discussions are given in terms of: reactor physics; reactor design studies; heat transfer and fluid now investigations; materials development; in- pile and out-of-pile testing of components and materials; and development of test loops and components. (B.O.G.)

Three self support, natural uranium, I & E production fuel elements, which exhibited serious in-reactor cladding corrosion were selected from several tubes of discharged pieces from PT-IP-272-A-FP. The elements were transferred to the Radiometallurgy Laboratory for detailed examination to determine thickness of the remaining cladding and measure any irradiation induced dimensional changes in the fuel cores. Each element had four support tabs attached to each end and was from Parent Lot KT.009. The fuel geometry of all three was C IV NS.

An O III N, I and E dingot element exhibited several transverse cracks when it failed in tube 2986 DR. Detailed examination in the Radiometallurgy Laboratory was requested to determine the cause of failure and obtain the ingot number. The element was so badly damaged that it was impossible to determine the exact cause of failure. Reaction between the coolant and fuel occurred at the internal surface around the spire over the total length of the element. Reaction was the greatest near the midpoint where the transverse cracks occurred and was least in the male end. Metallography of both longitudinal and transverse sections revealed that the metal quality of the fuel vas good. Cracks which originated from the oxide extended in both the longitudinal and transverse directions. The fuel near the core, which was insulated by oxide, was annealed but had not been heated into the uranium beta phase. One transverse crack which appeared to have water entry was observed approximately two inches from the male end. The ingot number was UZ 5751 B. After removal of the cladding at the ends, the uranium was bright dip etched and no defects were observed in the surface metal.

A direct numerical integration of the integral equation for the average collision density in the absorber was previously suggested in a discussion of resonance absorption. The implementation of this program is considered. The method of calculation, comparison with experimental data, and the computer code developed are described. The method of integration, computation of cross sections, selection of mesh size, integration interval, outside correction, the Dancoff correction, and unresolved resonances are discussed. Resonance integrals for U/sup 235/ and Th2/sup >/s3>s/sup 2/ were calculated and compared with experiment. (M.C.G.)

>Characteristics of the ORR, LITR, and OGR that experimenters have found to be important are listed. The results of a survey conducted among experimenters on the utility of the reactors for various types of experiments are discussed, and some changes which might be made to improve the utilization are listed. A brief outline, with references, of most of the experiments currently being performed is included. (auth)

This is a condensed version of an extended hazards safety review of a proposal to modify the six 8 3/8-inch lattice reactors on the Hanford site. The review was intended to satisfy the specifications for a Preliminary Hazards Review as adopted at the third meeting of the General Electric Technological Hazards Council at New York City on June 15-16, 1961. This supplement is a tabular condensation of the information in the general document. One departure is made from the specifications for such a review: since the overbore proposal is a modification to existent production reactors, those items which will not be changed by the modification are not as a rule included.

Early evaluation and study of the various criteria for the ORR clearly established the requirements for the fundarnental safety and control instrumentation, and the instrumentation was well integrated into the design and construction of the plant. However, it was not designed for the optimum of maintenance convenience and minimum reactor down time in the event of instrument failure. The revisions and additions that have been made in the physical plant and maintenance which have resulted in a definite reduction of reactor down time resulting from instrument failure in the reactor and in the experiments are described. (auth)

Declassified 26 Nov 1973. Fuel elements for the Tory II-C reactor are described along with fuel fabrication processes and mechanical and physical properties of the BeO-- UO/sub 2/ fuel materials. (JRD)