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Results:
1 - 24 of
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EVALUATION OF INCONEL 718 FOR APPLICATION IN THE FAST TEST REACTOR.
None
Date:
January 1, 1968
Creator:
Moen, R.A.; Wheeler, K.R. & Irvin, J.E.
Object Type:
Report
System:
The UNT Digital Library
Aerospace Nuclear Safety Program Quarterly Report, April 1-June 30, 1969.
This report describes research, development, support, and test activities in the Sandia Laboratory Aerospace Nuclear Safety Program from April 1 through June 30, 1969.
Date:
January 1, 1969
Creator:
Illing, R. G.
Object Type:
Report
System:
The UNT Digital Library
Advanced, Graphite-Matrix, Dispersion-Type Fuel Systems and Research on Graphite. Annual Report, April 1, 1964--March 31, 1965.
None
Date:
January 1, 1965
Creator:
Bokros, J. C.; Goeddel, W. V.; Lonsdale, H. K.; Price, R. J.; Tully Jr., G. R.; White, J. L. et al.
Object Type:
Report
System:
The UNT Digital Library
ANHARMONIC POTENTIAL CONSTANTS AND THEIR DEPENDENCE UPON BOND LENGTH
Empirical study of cubic and quartic vibrational force constants for diatomic molecules shows them to be approximately exponential functions of internuclear distance. A family of curves is obtained, determined by the location of the bonded atoms in rows of the periodic table. Displacements between successive curves correspond closely to those in Badger's rule for quadratic force constants (for which the parameters are redetermined to accord with all data now available). Constants for excited electronic and ionic states appear on practically the same curves as those for the ground states. Predictions based on the diatomic correlations agree with the available cubic constants for bond stretching in polyatomic molecules, regardless of the type of bonding involved. Implications of these regularities are discussed. (auth)
Date:
August 1, 1961
Creator:
Herschbach, D.R. & Laurie, V.W.
Object Type:
Article
System:
The UNT Digital Library
GAMMA-RAY ASSAY OF $sup 238$Pu IN WASTE CANS. PART I. SINGLE-CHANNEL ASSAY. PART II. MULTICHANNEL ASSAY.
None
Date:
January 1, 1969
Creator:
Strohm, W. W.; Combs, A. B. & Jarvis, J. Y.
Object Type:
Report
System:
The UNT Digital Library
Status Report on the Argonne Advanced Research Reactor
The interim design and development status is reported. The scope of the work was limited to conceptual design studies supported by critical experiments plus heat transfer and hydraulic tests. Design criteria, facility and site, reactor, core geometry and composition, fuel elements, reflector, core and reflector support structure, reactor vessel, control and instruments, primary coolant systems, secondary coolant system, auxiliary systems, experimental facilities, building layout and construction, plant ventilation, heating and air conditioning, critical experiments, reactor physics, heat transfer studies, and shieldings are discussed. (M.C.G.)
Date:
November 1, 1961
Creator:
Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
Object Type:
Report
System:
The UNT Digital Library
BURNUP DETERMINATION OF NUCLEAR FUELS. Project Report for the Quarter, April 1--June 30, 1968 and Final Report
None
Date:
March 1, 1969
Creator:
Lisman, F. L.; Maeck, W. J.; Rein, J. E.; Foster, Jr., R. E.; Abernathey, R. M.; Delmore, Jr., J. E. et al.
Object Type:
Report
System:
The UNT Digital Library
Preparation of Charge Materials for Ornl Electromagnetic Isotope Separators
SEPARATORS. C. W. Sheridan, H. R. Gwinn, and L. O. Descriptions are given of procedures, techniques, and equipment used to prepare charge materials for electromagnetic isotope separators at ORNL. Data on ion outputs during processing, charge consumption rates, and process efficiencies are given for 54 elements. (auth)
Date:
August 1, 1962
Creator:
Sheridan, C W; Gwinn, H R & Love, L O
Object Type:
Report
System:
The UNT Digital Library
RADIOACTIVE WASTE LOCATION VIA INFRARED SCANNING TECHNIQUES.
None
Date:
January 1, 1968
Creator:
Jensen, J D
Object Type:
Report
System:
The UNT Digital Library
Strontium-90 Fueled Thermoelectric Generator Power Source for Five-Watt U.S. Coast Guard Light Buoy. Final Report
The objectives of the SNAP 7A program were to design, manufacture, test, and deliver a five-watt electric generation system for a U. S. Coast Guard 8 x 26E light buoy. The 10-watt Sr/sup 90/ thermoelectric generator, the d-c-to-d-c converter, batteries and the method of installation in the light buoy are describcd. The SNAP 7A generator was fueled with four capsules containing a total of 40,800 curies of Sr/sup 90/ titanate. After fueling and testing, the SNAP 7A electric generating system was installed in the Coast Guard light buoy at Baltimore, Maryland, on December 15, 1961. Operation of the buoy lamp is continuous. (auth)
Date:
February 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Observations on the Effect of Selected Organic Materials on the Usable Potential Ranges of the Glassy Carbon, Pyrolytic Graphite, and Platinum Electrodes.
None
Date:
January 1, 1968
Creator:
Plock, C. E.
Object Type:
Report
System:
The UNT Digital Library
GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1961
Progress is reported on investigations in support of the Experimental Gas-Cooled Reactor, the Pebble-Bed Reactor Experiment, Advanced reactor design and development, test facilities, components, and materials. Topics covered include EGCR physics, EGCR performance analyses, structural investigations, EGCR component and materials development and testing, EGCR experimental facilities, PBRE physics and design studies, fueled-graphite investigations, clad fuel development, design studies of advanced power plants, experimental investigations of heat transfer and fluid flow, development of equipment anmd test facilities. and fabrication studies. (M.C.G.)
Date:
February 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Large Radioisotope Heat Source Capsule (LRHSC). Sixth Quarterly Progress Report, October--December 1968.
None
Date:
January 1, 1969
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Removal of $sup 137$Cs From Alkaline Condensate Wastes
None
Date:
January 1, 1968
Creator:
Mercer, B. W.; Ames, L. L. & Parkhurst, R. G.
Object Type:
Report
System:
The UNT Digital Library
AEC FUELS AND MATERIALS DEVELOPMENT PROGRAM. Seventh Annual Report.
This report is the seventh annual report of the unclassified portion of the Fuels and Materials Development Programs being conducted by the General Electric Company's Nuclear Materials and Propulsion Operation under Contract AT(40-1)-2847, issued by the Fuels and Materials Branch, Division of Reactor Development and Technology, of the Atomic Energy Commission. This report covers the period from January 31, 1967 to January 31, 1968, and thus also serves as the quarterly progress report for the final quarter of the year.
Date:
January 1, 1968
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
SURVEY OF REACTOR FACILITIES FOR PRESSURE TUBE IRRADIATION.
None
Date:
January 1, 1968
Creator:
Ard, P. A.; Heck, E. N. & McJilton, C. H.
Object Type:
Report
System:
The UNT Digital Library
Examination of Uranium-2 w/o Zirconium Experimental Fuel Slugs Irradiated in EBR-I. Final Report-Program 6.1.11
Six groups of U-2 wt% Zr fuel slugs were irradiated in the first core of the EBR-I to burnups of 0.080 to 0.189 at.% at calculated temperatures of 307 to 353 deg C. Two groups of cast specimens were found to be more dimensionally stable than four groups of wrought slugs. Of the wrought slungs, the as quenched group showed less tendency to grow than the three groups which had some annealing after quenching. Specimens at burnups of about 0.189 at.% and at 383 deg C showed the onset of swelling as indicated by density measurements. The hardnesses of these specimens seemed but little affected by radiation, but there was an indication of softening with increasing irradiation temperature. (auth)
Date:
February 1, 1962
Creator:
Murphy, W. F.; Klank, A. C. & Paine, S. H.
Object Type:
Report
System:
The UNT Digital Library
Pot Calcination Performance During First Radioactive Tests in Waste Solidification Engineering Prototypes: Waste Solidification Program. Vol. 4.
None
Date:
January 1, 1968
Creator:
McElroy, J. L.; Cooley, C. R.; DeMier, W. V.; Mendel, J. E.; Suddath, J. C. & Blomeke, J. O.
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961
Nine samples of ThO/sub 2/ -UO/sub 2/ prepared as part of the solgel process development studies showed no consistent effects from small variations in several process parameters. The reaction of methane and copper oxide was studied. Engineering studies of the continuous dissolution of simulated U-Zr-Sn fuels in 6.5 M NH4F, 0.6-1.0 M NH/sub 4/NO/sub 3/, 0.1 M H/sub 2/O/sub 2/ were continued in modified 6-in.-dia. equipment. A total of 1642 kg of U from NaK bonded SRE Core I fuel rods wad dejacketed to date/su Initial operability tests of the 250 ton prototype shear unit showed a number of minor modifications are warranted. Center tube temperatures measured in a vertical 64 tube electrically heated simulated fuel element bundle were very near those previously obtained in the horizontal position. A 304 SS tube containing eutectic NaK was dissolved by HF in fused saIt at a tube wall penetration rate of approximates 2 mils/hr. Partial differential equations were derived from the concentration of unreacted UF/sub 6/ as a function of time and position in a sphere of NaF during sorption of UF/sub 6/. Calcium nitrate solution was added directly to the pot calciner during Purex feeding to give smoother operation of the …
Date:
April 1, 1962
Creator:
Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type:
Report
System:
The UNT Digital Library
HRT CORROSION SAMPLES--ADDITIONAL DATA ON SPECIMENS REMOVED PRIOR TO RUN NO. 20
Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined include core screen samples, core specimen array No. 1, blanket specimen array No. 2, core solution line specimen arrays No. 103 and 103A, and blanket solution line specimen array No. 203. These data include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. A summary is included of the HRT operating schedule during exposure of the specimens and of the status of examinations for the specimens removed from the reactor prior to run 20. (auth)
Date:
February 1, 1961
Creator:
Baker, J.E.; Silverman, M.D.; Jenks, G.H. & Olsen, A.R.
Object Type:
Report
System:
The UNT Digital Library
Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre
The IBM 7090 program Murgatroyd is a revised and extended version of the IBM 704 program PET-I, which solves (by a fifth-order Runge-Kutta procedure) the coupled firstorder differential equations for power, delayed neutron concentration, and temperature in a one-region reactor as a function of time, given an input reactivity variation represented by a series of linear ramps. The basic extensions were those which were necessary to include the effects of the separate heat capacities and temperature coefficients of the fuel sait and graphite in the MSRE, and of heat transfer between the fuel and graphite. In addition, the input and output sections of the previous program were modified to facilitate the use of the program in extensive parameter studies, and a calculation of the pressure rise in the core was included. Typical running times are of the order of l2 milliseconds per time step; a calculation of a 30-second power history using a 10 millisecond time step requires about 36 seconds of machine time. (auth)
Date:
April 1, 1962
Creator:
Nestor, C. W. Jr.
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF A PROCESS FOR SODIUM BONDING OF EBR-II FUEL AND BLANKET ELEMENTS
Procedures for assembling EBR-II fuel elements with annular sodium bonds between the uranium rods and the stainless steel claddings are outlined. The results of several meltdown and uranium-settling experiments are given. Bonding experiments were performed: furnace bonding, submerged canning, ultrasonic bonding, centrifuging, pressure pulsing, and vibratory bonding. Vibratory bonding was chosen for the production of the first EBR-II core. (D.L.C.)
Date:
July 1, 1961
Creator:
Sowa, E.S. & Kimont, E.L.
Object Type:
Report
System:
The UNT Digital Library
BRAZING OF CERAMICS. Progress Report
Brazing alloys such as 48 Ti-48 Zr-4 Be (wt%) and 49 Ti-49 Cu-2 Be (wt%) have been found to readily flow on oxide and graphite ceramics. Two demonstrati on fuel element assemblies were fabricated to illustrate the usefulness of these procedures for nuclear applications. One of these assemblies contained graphite tubes and end caps which were brazed to a molybdenum hanger. The second demonstration fuel element was composed of a compartmented aluminum oxide plate to which aluminum oxide cover plates were brazed. (R.J.S.)
Date:
November 1, 1962
Creator:
Fox, C.W.
Object Type:
Report
System:
The UNT Digital Library
MULTI-NODE SIMULATION OF THE FFTF INTERMEDIATE HEAT EXCHANGER.
None
Date:
January 1, 1966
Creator:
Gerhardstein, L.H.
Object Type:
Report
System:
The UNT Digital Library