48 Matching Results

Search Results

Results: 1 - 24 next
open access

Compilation of the Melting Points of the Metal Oxides

Description: Report compiling the melting points of 70 metal oxides published prior to January 1963. Both the original melting point and the equivalent value based on the International Practical Temperature Scale of 1948 are presented. Included in the survey is information on pertinent experimental details such as the method of temperature measurement, purity, furnace type, and environmental conditions.
Date: October 10, 1963
Creator: Schneider, Samuel J.
Partner: UNT Libraries Government Documents Department
open access

Army Reactors Program Annual Progress Report: 1962

Description: Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Date: April 10, 1963
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
open access

In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C

Description: In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.
Date: June 10, 1963
Creator: Jenks, G. H.
Partner: UNT Libraries Government Documents Department
open access

Total Neutron Average Cross Sections in the KeV Region and the Optical Model

Description: The average total neutron cross sections for Nb, Mo, Rh, Ag, Cd, and In are measured at 10 to 100 kev, and the values obtained are used to calculate the optical-model parameters of the nuclei. The neutron energies used fall in the region of the P-wave giant resonances in these nuclei. (T.F.H.) 45Z6 The problem of the evolution of the amounts of nuclides during radioactive transformations is resolved according to the classical laws of radioactivity by using systematics in which the nuclides and … more
Date: September 10, 1963
Creator: Jain, A. P.; Chrien, R. E.; Moore, J. A. & Palevsky, H.
Partner: UNT Libraries Government Documents Department
open access

NEPTUNIUM RECOVERY AND PURIFICATION AT HANFORD

Description: From American Chemical Society Production Technology of Np-237 and Pu- 238, Denver, Jan. 1964. Neptunium is routinely recovered from irradiated fuel elements at Hanford's two main separation plants. Initial development tests were started in the Purex plant in 1958, then in the Redox plant in 1959, and recently culminated in the installation of new production systems in both plants for improved recoveries. Both recovery flowsheets employ solvent extraction techniques based on the relative extrac… more
Date: December 10, 1963
Creator: Isaacson, R.E. & Judson, B.F.
Partner: UNT Libraries Government Documents Department
open access

Shaped Burnable Poison Development Program Under the Euratom Program. Quarterly Progress Report, July 1, 1963-September 30, 1963

Description: The number and size of Gd/sub 2/O/sub 3/ poison cylinders were computed for a large boiling water reactor with H/sub 2/O-toUO/sub 2/ ratio of 2.6, a U/ sup 235/ enrichment of 3.3 wt%, and Zr clad. The excess reactivity of the poisoned core was computed for the cold-clean, hot-clean non-voided, and hot full- power condition as a function of Mwd/t. For comparison, these calculations were repeated for B/sub 4/C as the burnable poison element for the same reactor. The use of Gd rather than B/sup 10… more
Date: October 10, 1963
Partner: UNT Libraries Government Documents Department
open access

Investigation of Vapor Volume Fraction and Slip Velocity Under the Euratom Program. Quarterly Progress Report, July 1-September 30, 1963

Description: A literature survey was performed in order to provide an adequate basis for selecting models for comparison with the data. A computer program was written that allows calculation of void profiles based on an exponential model. A variable exponent is input data for the program, which also computes an integrated average void fraction. After the test section installation was completed, shakedown tests were performed to assure that all equipment was operating properly. All water and all air referenc… more
Date: October 10, 1963
Creator: Bezella, W. A.; Healy, M.; Kangas, G. J. & Neusen, K. F.
Partner: UNT Libraries Government Documents Department
open access

On the Spectral Theory of Singular Integral Operators

Description: A complete spectral representation is given for a class of singular integral operators. The influence of spectral multiplicity is partially taken into account. (T.F.H.)
Date: April 10, 1963
Creator: Pincus, J. D.
Partner: UNT Libraries Government Documents Department
open access

URANIUM SHOCK PROPERTIES

Description: Three shots were fired in the study of the low-pressure hydrodynamic behavior of U. Plots of target free-surface velocity vs. time are presented for various target thicknesses and pressures. The free-surface deceleration and second gradual acceleration are discussed. The calculation of rarefaction sound speeds is considered. Results are reported of an experiment using the capacitor technique to observe a reflected shock in U. (D L.C.)
Date: January 10, 1963
Creator: Taylor, J.W.
Partner: UNT Libraries Government Documents Department
open access

Laboratory reactor simulator

Description: No Description Available.
Date: December 10, 1963
Creator: Merchant, C.C. & Welsh, R.W.
Partner: UNT Libraries Government Documents Department
open access

Aerojet-general corporation report No. 2325

Description: This report talks about the Aerojet- general corporation report no. 2325
Date: January 10, 1963
Creator: Svasek, A. J.
Partner: UNT Libraries Government Documents Department
open access

LCRE and SNAP 50-DR-1 programs. Engineering progress report, January 1, 1963--March 31, 1963

Description: Declassified 5 Sep 1973. Information is presented concerning LCRE specifications, primary coolant circuit, aaxiliary systems, fuel elements, instrumentation, materials development, and fabrication; and SNAP-50DR-1 specifications, fuel elements, pumps, steam generator, and materials development. (DCC)
Date: June 10, 1963
Partner: UNT Libraries Government Documents Department
open access

Investigation of Vapor Volume Fraction and Slip Velocity Under the Euratom Program. Quarterly Progress Report, April 15, 1963-June 30, 1963

Description: Vapor volume fraction (void fraction) experiments using a gamma attenuation technique were planned. The experimental program required designing a test section and a steam generator. While the design of the test section was straightforward, the steam generator required considerably more attention because of the large flow and power requirements. Both designs were completed. All components of the gamma attenuation detection system were assembled and checked to be sure they were in proper operatin… more
Date: July 10, 1963
Partner: UNT Libraries Government Documents Department
open access

IMPROVED ZIRCONIUM ALLOYS. Quarterly Report, January 1, 1963-March 31, 1963

Description: On the basis of 4800 hr exposure to 680 l F water, a number of ternary compositions were shown to have corrosion resistance superior to Zircaloy-2. In addition, the strength and hydrogen pickup properties of the alloys were generally improved over Zircaloy-2. The promising alloys were based on the binary materials Zr- 1Sb, Zr- 1Cr, Zr0.5Nb, and Zr-0.5Sn to which small percentages of Te, Ge, Cr, or Fe were added. At present, 680 l F water corrosion data for an exposure time of 5000 hr are availa… more
Date: April 10, 1963
Creator: Weinstein, D. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
open access

SHAPED BURNABLE POISON DEVELOPMENT PROGRAM UNDER THE EURATOM PROGRAM. Quarterly Progress Report, December 1, 1962-February 28, 1963

Description: Nuclear cross section data for gadolinium, Gd/sup 155/, and Gd/sup 157/ were compiled. Average absorption cross sections were computed assuming Maxwellian thermal spectra for moderator temperatures from 70 to 600 deg F. Poison demand curves were computed for a boiling water reactor with an H/sub 2/O- to-UO/sub 2/ ratio of 2.6, U/sup 235/ enrichments from 1.8 to 3.8 wt%, zirconium or stainless steel as clad, and fuel depletions of 10,000 to 25,000 Mwd/t. Based on the above poison demand curves, … more
Date: April 10, 1963
Partner: UNT Libraries Government Documents Department
open access

Shaped Burnable Poison Development Program Under the Euratom Program. Quarterly Progress Report, March 1, 1963-June 30, 1963

Description: Poison demand curves were computed for a boiling water reactor with H/ sub 2/O to UO/sub 2/ ratios of 2.1 and 3.0, a uranium235 enrichment of 3.3 wt%, and fuel depletions in the range of 10,000 to 25,000 Mwd/t. These curves indicate poison lumps in the form of cylinders to be desirable. For these same reactors, the excess reactivity was computed for the cold clean, hot clean non- voided, and hot full-power equilibrium conditions. The excess reactivity was computed with and without a black burna… more
Date: July 10, 1963
Partner: UNT Libraries Government Documents Department
open access

STEAM SEPARATION TECHNOLOGY UNDER THE EURATOM PROGRAM. Quarterly Progress Report, January 1, 1963-March 31, 1963

Description: For purposes of analysis and experiment the centrifugal type downflow separator was divided into the inlet nozzle, separating zone, and outlet nozzle. The analysis and experiments have resulted in a new outlet design, a method of determining separating length, and a more effective inlet nozzle. The results have caused a reduction in pressure loss from 5 ft of water for the reference design to 1.5 ft of water for the new design at a flow rate of 1400 gpm. A reactor core riser and downcomer regio… more
Date: April 10, 1963
Partner: UNT Libraries Government Documents Department
Back to Top of Screen