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Aerospace Nuclear Safety Program Quarterly Report, April 1-June 30, 1969.
Description:
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.
Partner:
UNT Libraries Government Documents Department
Advanced, Graphite-Matrix, Dispersion-Type Fuel Systems and Research on Graphite. Annual Report, April 1, 1964--March 31, 1965.
Description:
No Description Available.
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.
Partner:
UNT Libraries Government Documents Department
GAMMA-RAY ASSAY OF $sup 238$Pu IN WASTE CANS. PART I. SINGLE-CHANNEL ASSAY. PART II. MULTICHANNEL ASSAY.
Description:
No Description Available.
Date:
January 1, 1969
Creator:
Strohm, W. W.; Combs, A. B. & Jarvis, J. Y.
Partner:
UNT Libraries Government Documents Department
Status Report on the Argonne Advanced Research Reactor
Description:
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 constructio…
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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.
Partner:
UNT Libraries Government Documents Department
BURNUP DETERMINATION OF NUCLEAR FUELS. Project Report for the Quarter, April 1--June 30, 1968 and Final Report
Description:
No Description Available.
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.
Partner:
UNT Libraries Government Documents Department
Preparation of Charge Materials for Ornl Electromagnetic Isotope Separators
Description:
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
Partner:
UNT Libraries Government Documents Department
RADIOACTIVE WASTE LOCATION VIA INFRARED SCANNING TECHNIQUES.
Description:
No Description Available.
Date:
January 1, 1968
Creator:
Jensen, J D
Partner:
UNT Libraries Government Documents Department
Strontium-90 Fueled Thermoelectric Generator Power Source for Five-Watt U.S. Coast Guard Light Buoy. Final Report
Description:
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 …
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Date:
February 1, 1962
Partner:
UNT Libraries Government Documents Department
Observations on the Effect of Selected Organic Materials on the Usable Potential Ranges of the Glassy Carbon, Pyrolytic Graphite, and Platinum Electrodes.
Description:
No Description Available.
Date:
January 1, 1968
Creator:
Plock, C. E.
Partner:
UNT Libraries Government Documents Department
GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1961
Description:
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…
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Date:
February 1, 1962
Partner:
UNT Libraries Government Documents Department
Large Radioisotope Heat Source Capsule (LRHSC). Sixth Quarterly Progress Report, October--December 1968.
Description:
No Description Available.
Date:
January 1, 1969
Partner:
UNT Libraries Government Documents Department
Removal of $sup 137$Cs From Alkaline Condensate Wastes
Description:
No Description Available.
Date:
January 1, 1968
Creator:
Mercer, B. W.; Ames, L. L. & Parkhurst, R. G.
Partner:
UNT Libraries Government Documents Department
AEC FUELS AND MATERIALS DEVELOPMENT PROGRAM. Seventh Annual Report.
Description:
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 f…
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Date:
January 1, 1968
Partner:
UNT Libraries Government Documents Department
SURVEY OF REACTOR FACILITIES FOR PRESSURE TUBE IRRADIATION.
Description:
No Description Available.
Date:
January 1, 1968
Creator:
Ard, P. A.; Heck, E. N. & McJilton, C. H.
Partner:
UNT Libraries Government Documents Department
Examination of Uranium-2 w/o Zirconium Experimental Fuel Slugs Irradiated in EBR-I. Final Report-Program 6.1.11
Description:
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…
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Date:
February 1, 1962
Creator:
Murphy, W. F.; Klank, A. C. & Paine, S. H.
Partner:
UNT Libraries Government Documents Department
Pot Calcination Performance During First Radioactive Tests in Waste Solidification Engineering Prototypes: Waste Solidification Program. Vol. 4.
Description:
No Description Available.
Date:
January 1, 1968
Creator:
McElroy, J. L.; Cooley, C. R.; DeMier, W. V.; Mendel, J. E.; Suddath, J. C. & Blomeke, J. O.
Partner:
UNT Libraries Government Documents Department
Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961
Description:
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 dejacke…
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Date:
April 1, 1962
Creator:
Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner:
UNT Libraries Government Documents Department
HRT CORROSION SAMPLES--ADDITIONAL DATA ON SPECIMENS REMOVED PRIOR TO RUN NO. 20
Description:
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 operati…
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Date:
February 1, 1961
Creator:
Baker, J.E.; Silverman, M.D.; Jenks, G.H. & Olsen, A.R.
Partner:
UNT Libraries Government Documents Department
Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre
Description:
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 temperatu…
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Date:
April 1, 1962
Creator:
Nestor, C. W. Jr.
Partner:
UNT Libraries Government Documents Department
DEVELOPMENT OF A PROCESS FOR SODIUM BONDING OF EBR-II FUEL AND BLANKET ELEMENTS
Description:
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.
Partner:
UNT Libraries Government Documents Department
BRAZING OF CERAMICS. Progress Report
Description:
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 pla…
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Date:
November 1, 1962
Creator:
Fox, C.W.
Partner:
UNT Libraries Government Documents Department
MULTI-NODE SIMULATION OF THE FFTF INTERMEDIATE HEAT EXCHANGER.
Description:
No Description Available.
Date:
January 1, 1966
Creator:
Gerhardstein, L.H.
Partner:
UNT Libraries Government Documents Department
The Effects of Irradiation on Some Binary Alloys of Thorium-Plutonium and Zirconium-Plutonium
Description:
A specimen of cast thorium-5 wt% plutonium and one of thorium-10 wt% plutonium were irradiated to total atom burnups of 1.9 and 2.6%, respectively, at maximum fuel temperatures of approximately 450 deg C. Both alloys displayed excellent dimensional stability with volume increases of 0.8 and 1.2% per atom per cent burnup, respectively. Three cold-rolled specimens of zirconium-5 wt% plutonium and one cold-rolled specimen of zirconium-7 wt% plutonium were also irradiated. The zirconium- plutonium …
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Date:
July 1, 1962
Creator:
Horak, J. A.; Kittel, J. H. & Rhude, H. V.
Partner:
UNT Libraries Government Documents Department
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2
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Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report
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Ames Laboratory, Iowa State University (IS)
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Fiscal Year 1966
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Fiscal Year 1969
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2
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Analog Simulation of the Hanford N-Reactor Plant
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Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures Quarterly Report
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Fuel Cycle Program Progress Report
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RME
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Saxton Plutonium Project Quarterly Progress Report
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