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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.
Item Type:
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Report
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.
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Report
ANHARMONIC POTENTIAL CONSTANTS AND THEIR DEPENDENCE UPON BOND LENGTH
Description:
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 el…
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Date:
August 1, 1961
Creator:
Herschbach, D.R. & Laurie, V.W.
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Article
Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report
Description:
An analytical trajectory and aerothermodynamic analysis of a satellite containing a Task 2 thermoelectric generator was completed. A 300-statute mile circular polar orbit was used for this analysis and the launch was assumed to be from Vandenberg Air Force Base. Results of this study show that upon natural decay from a successful mission, the radio-cerium fuel will burn up in space at high altitude, thus only a very minor amount of radio cerium will be released to the stratosphere. A complete a…
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Date:
December 27, 1960
Creator:
Oehrli, R.
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Report
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.
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Report
On Cratering: A Brief History, Analysis, and Theory of Cratering
Description:
Cratering is a subject that has been studied by many investigators for many years for many purposes. These purposes range from experimental studies of physical properties to large scale excavations using explosive charges of kiloton size. In the past ten years considerable effort has been devoted to cratering experiments for the purposes of determining the effects of cratering by nuclear explosions, with recent accent on Plowshare applications. From the large amount of data available for crater…
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Date:
August 22, 1961
Creator:
Nordyke, M. D.
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Report
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.
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Report
The Snap Ii Power Conversion System Topical Report No. 12. Boiler Development
Description:
The SNAP II boilers which were designed are summarized. As shown by test results from the three boilers which were tested, a continuous progress in design was achieved. These designs were based on test data from both the SNAP I and SNAP II programs. As the quantity of data increased, physical models describing the heat transfer process were developed. These physical models provide the necessary correlation parameters which permit the extension of existing data to advanced design. Preliminary te…
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Date:
July 17, 1961
Creator:
Gido, R. G.; Koestel, A.; Haller, H. C.; Huber, D. D. & Deibel, D. L.
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Report
Modified Purification System Performance Test. Core 1, Seed 2. Test Results T-641124-A. Section 2
Description:
The effectiveness of purification in controlling plant radioactivation rates was determined through comparison of the actual effects produced from plant operation with and without purification. With the purification system in service, there was no appreciable difficulty in maintaining the reactor coolant within reference water specifications. In addition, there was no discernible increase of crud deposition in the coolant system as determined by direct radiation measurements of the purification…
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Date:
July 21, 1961
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Report
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.
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Report
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
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Report
WELDING AND BRAZING OF HIGH-TEMPERATURE RADIATORS AND HEAT EXCHANGERS
Description:
Procedures were developed for fabricating highperformance radiators and heat exchangers for the Aircraft Nuclear Propulsion (ANP) Program. These components, which contain multitudes of tube-to-tube sheet and tube-to-fin joints, are similar in design to those under consideration for a variety of space vehicle applications. In order to ensure reliability of the tube-to-tube sheet joints, techniques producing welds of extremely high quality were used and back brazing of the welds with a suitable a…
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Date:
February 20, 1962
Creator:
Slaughter, G.M. & Patriarca, P.
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Report
RADIOACTIVE WASTE LOCATION VIA INFRARED SCANNING TECHNIQUES.
Description:
No Description Available.
Date:
January 1, 1968
Creator:
Jensen, J D
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Report
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
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Report
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.
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Report
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
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Report
Large Radioisotope Heat Source Capsule (LRHSC). Sixth Quarterly Progress Report, October--December 1968.
Description:
No Description Available.
Date:
January 1, 1969
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Report
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.
Item Type:
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Report
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
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Report
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.
Item Type:
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Report
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.
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Report
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.
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Report
Use of Analog Computers for Simulating the Movement of Isotopes in Ecological Systems
Description:
No Description Available.
Date:
January 24, 1962
Creator:
Neel, R. B. & Olson, J. S.
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Coal resources of western Pennsylvania
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Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures Quarterly Report
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Electrostatic Classification of Submicron Airborne Particles Progress Report
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Engineering Quarterly Progress Report, March, April, May 1962
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Enrico Fermi Atomic Power Plant Nuclear Test Series
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Fast Ceramic Reactor Development Program Summary Report
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1
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1
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Fuels and Materials Development Program Quarterly Progress Report
1
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High Temperature Materials and Reactor Component Development Programs Annual Report
1
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Historic UNT Webmap
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INEL Organic Reactor Technology Progress Report
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Idaho Nuclear Corporation Analytical Chemistry Branch Annual Report
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Irradiation Performance of Thoria-Urania Fuel Materials Quarterly Technical Report
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Metallurgy Division Annual Progress Report
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Saline Water Conversion Demonstration Plant Number 2
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Saline Water Conversion Demonstration Plant Number 2, San Diego, California, Annual Report
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Selected references 1962 - spring 1968
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7
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6
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1
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2
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7
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1
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2
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1
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2
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1
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1
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9
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1
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1
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2
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1
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2
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4
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5
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4
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4
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1
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1
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2
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4
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2
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1
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1
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1
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3
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1
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84
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2
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2
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2
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1
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1
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8,915
8915
2nd
97
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3rd
139
139
4th
100
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126
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166
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99
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