An IBM 1620 program is described that calculates the Bragg angles for cubic, hexagonal, and tetragonal crystal systems for use with powder x-ray diffraction techniques. Allowance is made for absent reflections in the case of face- and body-centered cubic and close-packed hexagonal materials.

An I.B.M. 1620 programme is described which calculates refined lattice parameters from X-ray diffraction data according to Hess' Method. The programme may be used for cubic, hexagonal, and tetragonal systems and three systematic error functions are included. The output includes the refined parameters their stand errors, and the misfit of the data at each experimental point.

This report explains details of the Advanced Materials Program. The purpose of this program is to develop improved alloys for nuclear powerplant structural applications in the 16000F to 2000F range and for advanced applications at temperatures to 2400F or above.

Annual report submitted by the Girl Scouts of the United States of America to Congress describing highlights from 1962, activities, organizational leadership, and other information about scouting programs.

Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.

; 8 7 < 8 < : : : 6 9 9 = < 9 < : 5 < > ;" icipation in the program continued to include review, inspection, and support in various areas of reactor technology. An advanced fuel irradiation test program was established that is to be conducted in the pressurized-water loop in the Oak Ridge Research Reactor. Review of the design of the MH-1A reactor was initiated. This reactor, a pressurized-water system fueled with low- enrichment bulk UO/sub 2/ clad with stainless steel, is being designed as a floating plant to furnish electrical energy to shore installations. Studies of the out-of-pile corrosion resistance of stainless steel brazed joints were completed. T-joint specimens of type 304 stainless steel were brazed together with 18 different alloys. Initial testing resulted in the selection of five of these alloys for extended testing, which was carried out in autoclaves with O/sub 2/ or H/sub 2/-O/sub 2/ added to the autoclave water. These alloys, General Electric alloys Nos. 81 and 75, Coast Metals alloy NP, low-melting Nicrobraz, and a Pdbase alloy, were satisfactory. Coast Metals alloy NP was selected as the reference braze material for the SM-1 fuel elements because it was …

Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.

The cadmium ratio was measured in an exponential mockup of Borax V as a function of the void fraction. The extent of voids, simulated by lengths of closed polyethylene tubes, ranged from 0 to 40%. The corresponding cadmium ratios ranged from 6.1 to 4.6. The exponential was also used to determine the radial flux pattern across a Borax-type fuel assembly and the fine flux detail in and around fuel rods. For a normal loading the maximum-to-average power generation across an assembly was 1.24. (auth)

On April 16, 1962, the fuel charge in overbore tube 3062-C sustained a failure, and upon examination after discharge was found to contain three split failures and three ``worm tracked`` elements (depression in the aluminum cladding apparently the result of uranium cleavage and subsequent yielding of the cladding). These failures occurred approximately ten days following a period of reactor neutron flux cycling, and during a second cycle at C Reactor. In addition to the failures, a total of 17 elements, from nine separate fuel charges, contained worm tracks. Four of these elements were sent to Radiometallurgy Laboratory for destructive examination, to determine the mechanism of the suspected uranium cleavage.

Seals capable of long life at 1500 c- C in cesium and vacuum environments are developed. Improved methods of sealing both metallized and unmetallized ceramic members to refractory metals are developed. Associated work on ceramics, refractory metal alloys, and ceramic-metal composites is made. (auth)

The properties of radioisotope fuel compounds and fuel capsule materials which are pertinent to the design and operation of radioisotope heat sources are outlined. These properties are grouped into the following categories: intrinsic, extrinsic, and compatibility. The properties of strontium titanate as the fuel and Hastelloy C as the capsule material are evaluated. (D.L.C.)

This report addresses the chemical characterization of selected core samples from the vicinity of Tatum Salt Dome, Lamar County, Mississippi.

This report, from the Chemical Processing Department at HAPO for March 1963, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and weapons manufacturing operation.

A distributed parameter transfer function is developed for SNAP type reactor cores. The coolant may be either boiling, non-boiling, or both. In the boiling case the Bankoff model is used to find the spatial distribution of voids. The transfer functions obtained are not simple polynomials. However, they are readily analyzed for stabilily using the 7090 program TRAFIC, which uses a Nyquist diagram approach. Some general conclusions resulting from these calculations are included. (auth)

A generalized correlation for the liquid fraction in twophase flow is presented which is proposed for use with all iluids, including liquid metals. The correlation is based on isothermal, two-phase, two-component liquid fraction data for liquid Hg--N/sub 2/ and water-air. Liquid fraction is shown to be a function of the Martinelli flow modulus and liquid/gas density and viscosity ratios. Good correspondence is indicated between the liquid fraction predicted by this correlation and the Martinelli-Nelson correlation for steam, experimental data for steam, and experimental data for Santowax R. Prediction of liquid fraction by this method is shown for Na, K, Rb, and Hg. Application of the method to boiling Hg, for a range of temperatures and exit qualities, is demonstrated for SNAP systems. (auth)

A small, lightweight, uranium carbide-fueled reactor with a beryllium reflector surrounding the core was mocked up as Assembly 40. It was determined that the presence of beryllium in the axial and radial reflectors did not endanger the safe loading and operation of the' critical assembly. The actual experiment consisted of determination of the critical mass, measurement of the reactivity coefficients for a large number of fissile and nonfissile materials, the performance of radial and axial fission traverses, and measurement of central fission ratios. The effectiveness of the radial beryllium reflectcr as a control mechanism was determined and the Rossialpha was measured. (auth)

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

This note describes a simple cryostatic device, which, by utilizing the latent heat of vaporization of liquid nitrogen, enables accurate control of temperature between ambient and - 150 degrees C. The advantages of this cryostat over other models known are simplicity of design and operation, ability to operate accurately from ambient to - 150 degrees C, economy, and large working space.

This bibliography represents the first cumulative edit of the literature examined by the Radiation Shielding Information Center recently established at the Oak Ridge National Laboratory. Its two major sections consist of a list of documents by subject category and of an author index. The document list covers nine major subjects with a total of 118 categories; however, literature specimens have not yet been entered for all categories. If a document applies to more than one category, it is listed under each. The author index includes cross references to the categories under which each author's publications appear. Preceding the bibliography is a list of the subject categories, their corresponding category numbers and the pages on which they appear in the bibliography,

These data are provided: Masses and .Mean Lives of Elementary Particles; Atomic and Nuclear Properties of Materials; Particle Scattering; Atomic and Nuclear Constants; Particle Decay and Reaction Dynamics; Tentative Data on Strongly lnteracting Particles and Resonances; and Clebsch-Gordan Coefficients and Spherical Harmonics.

This report addresses the decay heat cooling analysis of a nuclear rocket engine.

The purpose of this test was to determine the amount of deflection which could occur into the graphite cavity with a .032" thick sheet of 2219-T31 aluminum alloy.

A process was developed for the destruction of HNO/sub 3/ in Purex-type waste solutions using sugar. Polyhydroxy compounds such as sucrose, fructose, glucose, and crude syrups such as black strap molasses rapidly and controllably decompose HNO/sub 3/ in aqueous solutions at temperatures above approximately 85 deg C. The number of moles of HNO/sub 3/ destroyed per mole of sugar fed is a function of the temperature of reaction and the moles of dissolved multivalent metal cations (such as iron and chromium). The efficiency of HNO/sub 3/ destruction does not vary with acid concentration over the range of 0.5 to 8 M. However, destruction of acid does vary with iron concentration. Approximately 12 to 20 moles of HNO/sub 3/ are destroyed per mole of sucrose fed as the iron concentration increases from 0 to 1 M. Products of the denitration reaction are all gaseous, consisting of oxides of carbon and nitrogen. The process was successfully tested in the high level hot cells, the cold pilot plant denitration unit, and in the Purex plant. (P.C.H.)

The Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR- II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyrometallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5% fissium and contains about 46 wt.% U/sup 235/ . The blanket material consists of U in which plutonium is bred. Core and blanket subassemblies contained in transfer coffins are transferred between EBR- II and the Fuel Cycle Facility, which is in an adjacent building. The Fuel Cycle Facility consists primarily of an argon-atmosphere cell where fuel processing is done, an adjacent air-atmosphere cell where reactor subassemblies are assembled and disassembled, and an operating area (for personnel) which surrounds the two cells. Because of the high levels of activity expected, the fuel-handling-and- processing equipment is designed for remote operation. Remote processing is accomplished with the aid of bridge cranes, electromagnetic bridge manipulators, and master-slave manipulators. Transfer ports and air locks are used in the transfer of materials and equipment into the air-atmosphere cell and between the two cells. The walls between the argon-atmosphere and air-atmosphere cells and the operating …