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IMPACT EFFECT OF FRAGMENTS STRIKING STRUCTURAL ELEMENTS

Description: Equations were developed which permit a designer to evaluate the impact effect of a missile striking a structural element at high velocity. Examples of the use of the equations in calculations and comparisons of the relative effect of penetration on the equivalent static design load are included. Application to calculations of structural containnent for nuclear power plants is discussed briefly. (C. H.)
Date: January 1, 1957
Creator: Williamson, R.A. & Alvy, R.R.
Partner: UNT Libraries Government Documents Department

THOREX PILOT PLANT: SYSTEM FOR CONCENTRATING SECOND URANIUM

Description: A system for concentrating uranyl nitrate solutions was designed and installed in the Thorex Pilot Plant. A total of 16,060 g of uranium was concentrated in the system in 68 batch runs. A total of 14,400 g total uranium (14.180 g U/sup 233/) was recovered as product suitable for shipment. Uranium loss to the evaporator condensate was 0.03% of ihe total uranium processed. The material balance across the system was 98.4%. The average concentration of uranium in the evaporator feed solution was 29 g/liter; the average concentration in the evaporated solution was 298 g U/liter and in the product solution was 199 g/liter. Radiation readings of bottles containing product solutions were taken with a hard-shell cutie pie immediately after each run, and these readings ranged from 35 to 1100 mr/hr. The radiation levels of the bottles of product solution shipped averaged 78 mr/hr. Bottles of product solution reading in excess of 300 mr/hr, maximum allowable for shipment. were reprocessed in the second-cycle solvent extraction system (Thorex) and reconcentrated. The products from seven runs had radiation levels in excess of 300 mr/hr at the time of concentration, or the activities had grown to that level by the time of shipment. The procedures used in the operation of the above system are described in detail. (auth)
Date: January 28, 1957
Creator: Albrecht, W.L.
Partner: UNT Libraries Government Documents Department

PREPARATION OF THORIUM OXIDE FROM ORNL THOREX THORIUM NITRATE

Description: Thorium nitrate, removed from irradiated Th metal processed in the Thorex pilot plant, was converted to the oxide and then to the fluoride in one pilot-plant-scale and two laboratory-scale runs. Activity distributions, decontamination factors, and safety of the process are treated. (D.L.C.)
Date: February 13, 1957
Creator: McDuffee, W.T. & Yarbro, O.O.
Partner: UNT Libraries Government Documents Department

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR OCTOBER, NOVEMBER, AND DECEMBER 1956

Description: A study of mass transfer in a continuous-flow mixing chamber, fluoride volatilization separations process, corrosion testing in fused fluoride systems, behavior of Pu during volatilization of UF/sub 6/, preparation of PuF/sub 6/ by fluorination of PuF/sub 4/, particle size distribution and U content of UF/sub 4/ , stoichiometric behavior of the reaction IF/sub 5/ + F/sub 2/ + I/sub ignition data on stainless steel, were reported. Studies were continued on the analysis of crude green salt from U ore concentrates, fluidized-bed green salt pilot plant, calcination of reactor fuel wastes, reactor chemistry, chemical- metallurgical separation processes, waste processing operations, and the operation of the gammairradiation facility. (W.L.H.)
Date: March 1, 1957
Partner: UNT Libraries Government Documents Department

ELECTRONIC SPECIFIC HEAT OF SODIUM TUNGSTEN BRONZE

Description: The design and operation of a calorimeter for use in the temperature range 1.8 to 4.2 deg K are presented, and the methods used in the treatment of data and calculation of results are discussed. The heat capacities of several Na- W bronzes (Na/sub x/WO/sub 3/) were determined in the temperature interval 1.8 to 4.2 deg K. Samples having x equal to 0.89, heat capacities are described adequately by the sum of two terms, one linear and one cubic in temperature. The electronic specific heat of each sample is obtained by evaluating the coefficient of the linear term, and the Rebye eharacteristic temperature derived from the coefficient of the cubic term. Rensities of one-electron energy levels at the Fermi energy, and effective electronic masses are calculated from the electronic specific heats. A plot of the density of states as a function of energy can be made if it is assumed that this curve is independent of Na concentration. The justification of this assumption is discussed in the light of current theories of the solid state. The density of states curve rises rapidly at higher energies, and this rise is interpreted in terms of the filling of a Brillouin zone or of an overlap of two bands. (auth)
Date: March 1, 1957
Creator: Vest,R.W.; Griffel, M. & Smith, J.F.
Partner: UNT Libraries Government Documents Department

GRADED PLATE CARTRIDGE FOR PUREX A-TYPE EXTRACTION COLUMN

Description: Graded nonuniform cartridges are described which have plates with larger holes, greater free area, and/or greater plate spacing. These plates were developed and specified for the Purex Plant A-type columns. Use of the cartridges eliminated cyclic local flooding and increased the complete flooding frequency by 10 and 25 cycles/min at volume velocities of 530 and 1060 gal/hr/ sq ft, respectively, and exhibited satisfactory extraction efficiency over a wide range of frequencies and throughputs. (auth)
Date: March 20, 1957
Creator: Geier, R.G. & Hesson, G.M.
Partner: UNT Libraries Government Documents Department

HAZARDS SUMMARY REPORT ON THE OXIDE CRITICAL EXPERIMENTS

Description: A new zero-power reactor facility, designated as ZPRVII, which is under construction at the Argonne National Laboratory is described. This facility will be used to supply physics design information required in connection with several phases of Argonne's boiling reactor program. A description of the first reactor system to be investigated in this facility and an assessment of the hazards associated with the planned program of measurements are included. The first system to be investigated will employ fuel in the form of pellets of a fired mixture of enriched UO/sub 2/ and ThO/sub 2/. These pellets will be approximately 1/4 in. in diameter, stacked to a height of 5 ft within an Al jacket of 5/16-in outer diameter. These fuel rods will be grouped in a variety of arrangements within a 6 3/4-ft diameter tank which can be filled with D/sub 2/ O. The construction instrumentation, and control system of the Z PR-VII conform with past practice at Argonne. This reactor system is unusually safe as a consequence of large negative temperature and void coefficients of reactivity. Large reactivity effects are virtually impossible to achieve other than through deliberate sabotage, and the inherent safety mechanisms make the reactor completely self-limiting with no damage for a 1% excess reactivity step and probably for a 2% step. In addition the public hazard associated with an appreciably greater reactivity step is extremely small. (auth)
Date: April 1, 1957
Creator: Redman, W.C.; Thie, J.A. & Dates, L.R.
Partner: UNT Libraries Government Documents Department