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Distribution of selected lanthanides and actinides between 30% TBP in n- paraffin and various metal nitrate solutions

Description: Distributions were measured for nitric acid, americium, curium, cerium, neodymium, samarium, europium, manganese, and mercury between 30 vol % THP in n- paraffin and aqueous solutions containing nitric acid, aluminum nitrate, lithium nitrate, and/or sodium nitrate. Equations for the distributions were derived from the data and used in designing solvent extraction flowsheets for recovery and decortamination of americium and curium from irradiated plutonium- aluminum alloy. Also investigated was the effect of DTPA acid on the distribution of the actinides and lanthanides in the same systems. The actinides (Am and Cm) are more strongly complexed than the light lanthanides (La, Ce, Pr, and Nd) by DTPA acid. By controlling the solution pH in the range of 1 to 3, separation of actinides from lanthanides by factors of 10 to 100 may be obtained by extraction with 30% THP. (auth)
Date: November 1, 1973
Creator: Thompson, M.C.
Partner: UNT Libraries Government Documents Department

Effect of trapping on hydrogen permeation in copper

Description: From international conference on hydrogen embrittlement effect on metal properties selection and design; Champion; Pennsylvania, USA (23 Sep 1973). Results of permeation experiments with high-purity copper in a deuterium atmosphere suggest that reversible trapping of deuterium occurs. Deuterium permeation was measured at temperatures between 270 and 450 deg C. A mathematical model, based on the general diffusion-plus-trapping model of McNabb and Foster, was developed to predict trap densities. Solutions were obtained for a plane sheet by the finite-difference method and are convergent and stable over a relatively wide range of parameters. Experimental results agree qualitatively with predictions of the model. (auth)
Date: January 1, 1973
Creator: Caskey, G.R. Jr. & Pillinger, W.L.
Partner: UNT Libraries Government Documents Department

Bivanes and flying tails

Description: No Description Available.
Date: January 1, 1974
Creator: Pendergast, M.M. & Schubert, J.F.
Partner: UNT Libraries Government Documents Department

Californium oxide--palladium cermet wire as a $sup 252$Cf neutron source form

Description: An improved /sup 252/Cf neutron source form has been developed to enhance containment of /sup 252/Cf during production of the sources and to lower the sale price of /sup 252/Cf sources by commercial encapsulators. Process steps are described for preparing califomnium oxide-palladium cermet powder by palladium chemical plating, fabrication of cermet pellets by pressing and sintering, fabrication of bare wire by rolling, and adjustment (reduction) of / sup 256/Cf linear concentration by roll cladding. /sup 252/Cf is distributed uniformly in the wires, which can be made in concentrations suitable for a full range of industrial source strengths (from 1 x 10/sup 7/ to 2.6 x 10/sup 10/ n/ sec). These processes were developed in laboratory tests with stead-ins and /sup 252/Cf tracer, and were demonstrated with milligram quantities of /sup 252/Cf in the Target Fabrication Facility (TFF). Improved wire forming techniques are being developed to manufacture clad wire on a larger scale. (auth)
Date: January 1, 1974
Creator: Mosley, W.C.; McBeath, P.E. & Smith, P.K.
Partner: UNT Libraries Government Documents Department

Desk-top microcomputer

Description: No Description Available.
Date: August 1, 1974
Creator: Byrd, J.S.
Partner: UNT Libraries Government Documents Department

Dissolving uranium oxide--aluminum fuel

Description: The dissolution of aluminum-clad uranium oxide-aluminum fuel was studied to provide basic data for dissolving this type of enriched uranium fuel at the Savannah River Plant. The studies also included the dissolution of a similar material prepared from scrap uranium oxides that were to be recycled through the solvent extraction process. The dissolving behavior of uranium oxide-aluminum core material is similar to that of U-Al alloy. Dissolving rates are rapid in HNO/sub 3/-Hg(NO/sub 3/)/sub 2/ solutions. Irradiation reduce s the dissolving rate and increases mechanical strength. A dissolution model for use in nuclear safety analyses is developed, . based on the observed dissolving characteristics. (auth)
Date: November 1, 1973
Creator: Perkins, W.C.
Partner: UNT Libraries Government Documents Department

Heat Transfer Laboratory of the Savannah River Laboratory

Description: The Heat Transfer Laboratory, recently- constructed adjacent to the main Savannah River Laboratory building, was designed to mock up nuclear heating and cooling of reactor components under a variety- of conditions. Nuclear heating is simulated by electrical resistance heating of test sections with a 3 MW directcurrent power supply. Cooling is provided by water. Three test stations (A, B, and C) are available for testing full-size fuel assemblies, measuring flow instabilities, and for measuring burnout heat fluxes. Safeguards provided in the design of the facility and conservative operating procedures minimize or elimnate potential hazards. (auth)
Date: October 1, 1973
Creator: Knoebel, D.H. & Harris, S.D.
Partner: UNT Libraries Government Documents Department

PRELIMINARY REPORT ON 2% U$sup 235$-ENRICHED UF$sub 4$-C$sub 25$H$sub 52$ CRITICAL ASSEMBLIES

Description: A series of critical experiments with blocks of 2% U/sup 235/--enriched UF/sub 4/-C/sub 25/sub 5/H/sub 52/ was initiated at the ORN L Critical Experiments Facility. Thus far assemblies with H:U/sup 235/ atomic ratios of 195 and 294 were built in parallelepipedal and simulated cylindrical geometries, both reflected and unreflected. From the results the minimum critical masses for reflected spheres were determined to be 16.3 and 8.5 kg of U/sup 235/ for fuel mixtures with H:U atomic ratios of 195 and 294, respectively. The minimum critical masses for unreflected spheres of these two fuel mixtures are 24.3 and 12.7 kg of U/sup 235/ respsctively. (auth)
Date: April 22, 1959
Creator: Mihalczo, J T; Lynn, J J; Scott, D & Connolly, W C
Partner: UNT Libraries Government Documents Department

DESIGN OF MODIFIED QUADRUPOLE MAGNETS

Description: Modifications to the shape of ideal quadrupole magnets were investigated, using an electrolytic tank method. Magnets with straight and with exponential pole faces were considered with 1: 1, 1: 2, and 1:3 apertures. The additional field introduced by these modifications was expressed in an harmonic series and the coefficients of this series plotted against the parameters characterizing the modifications made. (auth)
Date: November 1, 1962
Creator: Goitein, M
Partner: UNT Libraries Government Documents Department

POWER AND TEMPERATURE OF TBR FOLLOWING INTERRUPTION OF NORMAL OPERATION

Description: Calculations were performed to determine the behavior of the TBR under certain conditions involving interruption of normal operation. The situations considered are sudden stoppage of circulation in the core circuit, sudden cessation of heat removal in the heat exchanger, and circulating pump failure. The first two situations result in a rapid, hazardous temperature rise; no danger appears in the third condition. (D.E.B.)
Date: September 27, 1955
Creator: Rosenthal, M W
Partner: UNT Libraries Government Documents Department

POWER REACTOR FUEL REPROCESSING PROCESS WASTES

Description: Data on waste volumes and heat generation of several reactor fuels which may be reprocessed in the Power Reactor Fuel Reprocessing Pilot Plant at ORNL are tabulated. (auth) l6876 A tabulation containing information on the power of existing and proposed U. S. and U. S.-built reactors of 10 kw or greater thermal power is presented. Estimated fuel reprocessing loads for irradiated fuels are also iucluded. (auth)
Date: June 19, 1959
Creator: Conger, W L
Partner: UNT Libraries Government Documents Department

POWER REMOVAL FROM A BOILIGN REACTOR

Description: BS>This work is based on a rather specific and simplified model of the reactor core in which internal circulation exists. Because of the model simplicity, the influence varying some of the parameters appears more directly. In particular, calculation of the circulation factor, which is important in determining the need for vapor separators is included. On this basis it was felt desirable to make the results of this study available even though they have been largely superseded by the later work. (auth)
Date: October 1, 1952
Creator: Zmola, P. C. & Lawson, E. N.
Partner: UNT Libraries Government Documents Department