Serial/Series Title
Chemical Processing Department Monthly Report
60
Irradiation Processing Department Monthly Report
25
Notes of Monthly Component Test Program Review Meeting Held with SNPO at WANL
25
Hanford Laboratories Operation Monthly Activities Report
24
ANL Reactor Development Program Progress Report
14
Project Chariot
13
Project Sedan
11
Pacific Northwest Laboratory Monthly Activities Report
8
Project Pre-Schooner 2
8
ACRH Semiannual Report on Medical Research
7
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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
Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report
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 analyses of the fate of the radio-cerium fuel following various aborted launching attempts also was carried out. Charts summarizing the various assumed failures and locations of the fuel following failure are shown. A technical discussion of the methods used in performing the analysis is included in the report. (auth)
Date:
December 27, 1960
Creator:
Oehrli, R.
Object Type:
Report
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
On Cratering: A Brief History, Analysis, and Theory of Cratering
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 craters in alluvian has been possible to establish very reliable relationships between charge size, depth of bursty crater radii, and crater depths. In addition it has been possible to construct a preliminary theory of the mechanics of explosive crater formation. The available experimental data for nuclear and high explosive craters are reviewed, with particular emphasis on the data for desert alluvium, and the pertinent relationships are derived. A theory of the important cratering mechanisms, which has been evolved on the basis of these data and data from other sources, is outlined. (auth)
Date:
August 22, 1961
Creator:
Nordyke, M. D.
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
The Snap Ii Power Conversion System Topical Report No. 12. Boiler Development
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 test sections were designed on the assumption that an allvapor nmodel which ignores the presence of the liquid phase during forced convection boiling could be used to describe the process quantitatively. The conventional Dittus-Boelter equation was applied with the increase in the vapor flow along the tube being ascribed to liquid evaporation. The assumption led to a design that fell short by about an order of magnitude since the exit qualities were only in the range of 10%, far less than required for complete vaporization. As a result, a revision in the concept of the mechanics of boiling was found necessary and a theoretical analysis was formulated, based on a dry wall'' or dropwise'' type boiling phenomenon. The test results of the …
Date:
July 17, 1961
Creator:
Gido, R. G.; Koestel, A.; Haller, H. C.; Huber, D. D. & Deibel, D. L.
Object Type:
Report
System:
The UNT Digital Library
Modified Purification System Performance Test. Core 1, Seed 2. Test Results T-641124-A. Section 2
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 hairpin loop. However, without demineralization as a controlling agent, the gross non-volatile gamma activity levels of the reactor coolant increased and the specific activities of longlived fission products were at higher levels. Although the general levels of water- borne activities increased during the test period, the associated plant systems did not exceed their limits. (auth)
Date:
July 21, 1961
Creator:
unknown
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
WELDING AND BRAZING OF HIGH-TEMPERATURE RADIATORS AND HEAT EXCHANGERS
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 alloy was incorporated. High-temperature brazing was also incorporated to attach high-conductivity fins to Inconel tubes in the radiators. The selection of a suitable brazing alloy for these applications was dependent upon several factors, including corrosion and oxidation resistance, flow point, and mechanical properties. A Ni- Si-B alloy was found to be adequate from all these considerations. Special brazing procedures were developed to obtain satisfactory flowability of this brazing alloy on tube-to-fin joints. The suitability of these fabrication procedures for the very stringent service conditions to which the radiators and heat exchangers were subjected was demonstrated by testing full-size components under operating conditions. (auth)
Date:
February 20, 1962
Creator:
Slaughter, G.M. & Patriarca, P.
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
Use of Analog Computers for Simulating the Movement of Isotopes in Ecological Systems
None
Date:
January 24, 1962
Creator:
Neel, R. B. & Olson, J. S.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library