A preliminary design study, Phase I of the ALPR project, has been made in accordance with the Army Reactors Branch specifications for a nuclear "package" power plant with a 200-260-kw electric and 400 kw heating capacity. The plant is to be installed at the Idaho Reactor Testing Station as a prototype for remote arctic installations. The "conventional" power plant as well as the exterior reactor components are described in the accompanying report and cost estimate by Pioneer Service and Engineering Company, Architect-Engineers for the project."Nuclear" components of the reactor are designed by Argonne National Laboratory as described in the present report.

Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.

Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations.

Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.

On October 7, 8, and 9, 1953, the Atomic Energy Commission Division of Reactor Development held a reactor information meeting at the Argonne National Laboratory. The objective of the meeting was exchange of information among people actively concerned with the design of reactors for power to the end that the power reactor program would move more speedily and more economically to another milestone of success. In this volume all the papers presented at the meeting are listed. Copies are given of those papers which are available, and references to published reports are indicated where know for those papers not included in this collections. In order to facilitate handling, this volume is being issued in six parts: Part I Power Reactors; Part II Reactor Physics. Critical and Exponential Experiments Measurements; Part III Reactor Components. Reactor Economics Considerations. Reactor Safeguard and Control; Part IV Fuel Element Design and Problems. Corrosion and Chemistry; Part V Heat Transfer; Part VI Processing. The Author Index is being bound and distributed with Part I of this volume.

The fuel element to be used in the Savannah River reactors is a natural uranium slug 1.00 in. in diameter and 8 in. long, encased in a 2S aluminum can 1.080 in. O.D. having a wall thickness of 0.035 in. The slug is bonded to the can with an aluminum silicon alloy, using the Hanford Al-Si process.

This technical report describes experimental nuclear physics, mass spectroscopy, crystallography, experimental reactor physics, theoretical physics (general), reactor theory and electronic digital computers.

This quarterly report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses water cooled reactors, liquid metal cooled reactors, reactor development metallurgy, basic metallurgy, applied metallurgy, and aqueous corrosion,

This technical report describes the design and construction of equipment and the development of methods for multiple mold, centrifugal casting of reactor fuel slugs. Advantages of the centrifugal casting method over the conventional fabrication methods were found to be (1) fewer operations, (2) fewer and more easily recovered residues, (3) less expensive equipment, and (4) the production of fuel slugs in shapes and in alloys not well adapted to other methods of manufacture. The method consisted of vacuum melting the alloy in stoppered crucibles and bottom pouring into a spinning rotor carrying 16 radially arranged copper molds. The castings so produced were used without further processing, except for cropping the sprue end to obtain the specified length.

This technical report describes experimental nuclear physics, mass spectroscopy, crystallography, experimental reactor physics, theoretical physics (general), reactor theory, electronic digital computers, and applied mathematics and computations (general).

The feasibility of cladding plate type, corrosion resistant uranium-niobium fuel elements with Zircaloy-II by roll bonding has been demonstrated. Plates with cores of uranium alloyed with 3 w/o and 6 w/o Nb intended for irradiation testing in a high temperature water test loop in the MTR have been finished withing specified tolerances. The preparation of cladding billet core and clad components and the assembly of billets by enclosing cores in welded Zircaloy-II jackets can be readily accomplished with conventional fabrication equipment. Some machining operations and billet evacuations, as used in the preparation of most picture frame billet assemblies have been eliminated. Roll bonds were obtained with reductions of 75% to 80% in thickness. Reductions in excess of 90% in thickness, although not necessary for bonding , can be used for economical productions of long plates. Plates can be made with clad to core bond strengths from 30,000 psi to 60,000 psi. Properly heat treated plates have sufficient ductility to allow cold finishing by rolling, forming, bending, or twisting, with reductions of 20% to 30%. Edge bonds of Zircaloy to Zircaloy have been obtained which were corrosion resistant to 260 C water. End seals which were also corrosion resistant to water …

Water corrosion tests on mechanically jacketed and pinholed thorium slugs show that these slugs fail in a manner similar to that observed for mechanically jacketed and tested uranium slugs. The proposed mechanism for the water corrosion of these jacketed slugs is analogous to the water corrosion mechanism of jacketed uranium slugs presented in the project lecture. A bare thorium slug appeared to be more resistant to corrosion by water than a mechanically jacketed slug during the first half of the autoclave test. After approximately 90 hours of testing both the bare and the mechanically jacketed thorium slugs were severely corroded by water.

This supplement includes reports on (1) transmission measurements with the fast chopper, (2) a search for Pu244, (3) crystallographic studies, (4) resonance flux in CP-[gamma], (5) multigroup methods for concentrated fast assemblies, (6) work on the ZPR-1 Reactor, and (7) work on the ZPR-II Reactor.

A fuel element assembly in which a uranium slug is bonded to an impact extruded aluminum can by means of aluminum-silicon eutectic, and in which the can is capped with a thin aluminum disc, brazed and welded to the can, may contain,(a) imperfections common to brazed and welded metal sections, and (b) inhomogeneities arising from oxidation of uranium, and alloy formation between uranium, aluminum and silicon.

An analytical method has been developed for zirconium and fluoride ions in the system resulting from the dissolution of fuel elements in hydrofluoric acid. The method is based on determination of the density and electrical conductivity of the dissolved metal solution.

The tests described in this report were static tests devised to afford a basis for a quick evaluation of the resistance of uranium to attack by lithium. The work was done at the same time as the tests of beryllium, thorium, and various engineering metals in lithium (described in ANL-4990); but the results with uranium are given in the present classified report so that the results of the other tests can be published as an unclassified document. The procedure for carrying out the tests is described in ANL-4990.

The results of this study are tabulated in Summary Tables A and B below. For the most part, these values were read from smoothed curves drawn thru the plotted experimental data. The values for aluminum (i.e., 0 w/o Li) were taken from the 1948 Edition of the ASM Metals Handbook. The room temperature properties are reported for lithium contents of 0, 3.5, 7 and 10 weight per cent. In the case of the high temperature properties, there were insufficient data to allow extrapolation and interpolation to pre-chosen compositions: these properties are therefore reported only for the compositions of the actual samples.

This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) effects of radiation on ice -- the x-ray induced luminescence of ice, (1.5) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (2.2) application of mass spectrometry to chemical problems, (2.3) vapor pressure and heat of vaporization of uranium, (3.1) nuclear properties of Zr93 and Nb93m from fission, (3.2) mass distribution in the spontaneous fission of Cm242, (3.3) Upper limit to the lifetimes of the first excited states of Th236, U234, and Pu236, (3.4) on the one-body model of alpha radioactivity, (4.1) spectrographic analysis, (4.2) chemical analysis, (5.1) paramagnetic resonance measurements, and (5.2) the 60-inch cyclotron.

The Helium Leak Detector Test provides a method for detecting the presence of minute holes, cracks, fissures, etc. in the aluminum jackets of Hanford and Savannah River reactor fuel slugs which would allow moisture to penetrate to the uranium during reactor operation.

On June 2, 1952, 15:52 hours, a large reactivity change was made manually in a ZPR-1 assembly causing a power excursion of about one kwh, which resulted in damage to the reactor core components and radiation exposure of some of the operating personnel to perhaps several rep. None of the contributing causes is reviewed here nor are the measures which were taken to reduce the probability of a recurrence discussed since these are considered administrative matters beyond the scope of this technical report. It is intended only to describe the incident, estimate the exposures and present available clinical data.

This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses (1) water-cooled reactors, (2) liquid metal-cooled reactors, (3) reactor development - fuel metallurgy, (4) reactor development - component metallurgy, (5) basic metallurgy, (6) basic ceramics, (7) aqueous corrosion, and (8) applied metallurgy.

Corrosion rates of present reactor grade uranium were measured in boiling distilled water and were found to have higher values almost by a factor of two then previously reported corrosion rates of uranium. Mallinckrodt biscuit metal showed corrosion rates in the same medium somewhat lower than reactor grade uranium, and high purity metal prepared at Argonne National Laboratory corroded considerably less rapidly than the biscuit metal.

This technical report describes work done on the electrolytic refining of natural uranium in fused salt baths composed of various eutectics of alkali metal chlorides in which were dissolved UF, or UCl3.