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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… more
Date: July 17, 1961
Creator: Gido, R. G.; Koestel, A.; Haller, H. C.; Huber, D. D. & Deibel, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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… more
Date: July 21, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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 … more
Date: July 1, 1962
Creator: Horak, J. A.; Kittel, J. H. & Rhude, H. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SOLUBLE NEUTRON POISONS AS A PRIMARY CRITICALITY CONTROL IN SHIELDED AND CONTAINED RADIOCHEMICAL FACILITIES

Description: Studies indicated that the use of soluble poisons as a primary criticality control offers economic and other advantages in that it permits the factors of vessel size and shape and solution concentrations to be dictated by considerations other than those of criticality. It is believed that soluble poison criticality control can be made as reliable as other methods of coaditional control if the application is preceded by adequate development work and is monitored by multiple. independent safeguar… more
Date: July 26, 1962
Creator: Nichols, J.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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APPLICATIONS OF SNAP REACTOR SYSTEMS TO COMMUNICATIONS SATELLITES

Description: Methods are presented for determining the electric power requirements of a given communications mission in terms of mission and orbit parameters. Analyses were made of possible applications of available and projected space auxiliary power units in these satellites. The satellitc as a communication node is discussed. Example calculations are given. (M.C.G.)
Date: July 30, 1962
Creator: Wimmer, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurements and Changes on SM-1 Core II During Period October 1, 1961 to May 30, 1962

Description: Tests at the SM-1 reactor are reported for the period October 1, 1961, to May 31, 1962. Loading changes were made in SM-1 Core II during the scheduled semiannual shutdowns in October to November 1961 and April to May 1962. Core physics tests include control rod bank calibrations, bank position at several temperature and xenon poison conditions vs core changes and energy release, shutdown neutron source decay and startup channel testing, and critical rod positions for stuck rod configurations. S… more
Date: July 1, 1962
Creator: Motte, F. G.; Best, W. C. & Kortheuer, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PHYSICS ANALYSIS OF THE JUGGERNAUT REACTOR

Description: The JUGGERNAUT is an intermediate-power research reactor designed and constructed as a supporting facility for chemistry and physics research. The design of this reactor is similar to that of the ARGONAUT, and those methods of evaluating the nuclear characteristics of the ARGONAUT which gave good agreement with experimental data were considered applicable to the analysis of the JUGGERNAUT. The analyses for both the JUGGERNAUT and the ARGONAUT were based on a modified two-group theory. The criti… more
Date: July 1, 1962
Creator: Moon, D.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SPERT IV HAZARDS SUMMARY REPORT

Description: Spert IV is a large pool-type experimental facility for reactor kinetic studies. These studies will include power excursion and instability tests for a variety of reactor designs. Since the Spert IV experimental program requires the performance of tests which will approach, and may exceed the threshold of reactor destruction, the probability of occurrence of the maximum possible accident is not negligible compared with that of other possible accidents. The maximum possible accident for this fac… more
Date: July 1, 1961
Creator: Bentzen, F. L. & Crocker, J. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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OXIDATION OF GRAPHITE UNDER HIGH TEMPERATURE REACTOR CONDITIONS

Description: A kinetic study was conducted to provide information on oxidation of reactor graphites in the temperature range of 450 to 675 deg C and on the effects of reactor environment on oxidation rates. Among the parameters studied were chemical reactivity of the graphite, prior oxidation, a high intensity gamma flux during oxidation, variation of the surface-to-volume ratio of the graphite specimens, neutron bombardment prior to oxidation exposure, and gas flow rates. Rate equations showed apparent act… more
Date: July 1, 1961
Creator: Dahl, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL MEASUREMENTS OF THE SUCTION HEAD REQUIRED BY THE HALLAM PROTOTYPE FREE SURFACE SODIUM PUMP

Description: Hydraulic tests were made on the Hallam Prototype Free-Surface Sodium Pump to determine the net positive suction head (NPSH) required at various sodium flow rates. Pump performance data were also collected. The results indicate that an NPSH of 22 ft sodium is required at the design flow rate of 7200 gpm at approximates 1000 deg F, agreeing with computed values, and that the pump is designed with a safety margin of slightly over l0%. (D.L.C.)
Date: July 25, 1961
Creator: Atz, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Proceedings of the 1960 Idaho Conference on Reactor Kinetics Held at Sun Valley, Idaho, October 12-14, 1960

Description: >Thirty papers are included on reactor kinetics with emphasis being placed on reactor safety and design considerations resulting from kinetic work. Information is presented on power excursion programs, reactor transfer function determination and application, reactor instability and thermal-hydraulic problems, and analytical methods in reactor kinetics. The accomplishments in the field and areas needing emphasis are discussed and summarized. Constructive suggestions are made on program direction… more
Date: July 1, 1962
Creator: Haire, J. C. & Bright, G. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Use Test Comparison of TBP Diluents

Description: Several diluents for possible use in TBP Purex Plant solvent were tested. The tests included nitric --nitrous acid degradation, fission prcduct distribution under simulated plant conditions, emulsillcation, and radiolysis. The order of quality of four diluents is n-dcdecane> Soltrol 170> Shell Code 85030(82000)> Shell E-2342. (D.L.C.)
Date: July 1, 1961
Creator: Mendel, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Detailed Stress Analysis of SM-1 Steam Generator Tube Sheet

Description: The detailed stress analysis of the SM-1 steam generator tube sheet showed it to be safe from strain cycling damage. However, the pressure stresses were greater than the yield strength during the hydrostatic test. The differential between pressure stresses and yield strength indicates that some initial deformation may have taken place in the tube sheet. (auth)
Date: July 11, 1962
Creator: Busuttil, J. J. & Chittum, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spectrophotometric studies of solutions at elevated temperatures and pressures: status and program for FY1961 and part of FY 1962

Description: A program was initiated on the spectrophotometric study of aqueous solution chemistry. The goal is operation at temperatures up to at least 330 deg C and at pressures up to 200 atm, and to near the critical point if this appears to be feasible. A spectrometer capable of operation under these extreme conditions is being designed. (W.L.H.)
Date: July 19, 1960
Creator: Biggers, R. E. & Chilton, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Presidential Inaugurations: The Case of Inaugural Dates Falling on Sunday

Description: This report's purpose is to present the constitutional and historical background of the "interregnum" question and to describe the precedents established on these occasions. It discusses when the date set for the inauguration of the president has fallen on a Sunday.
Date: July 8, 1968
Creator: Beebe, Ronald
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A SURVEY AND EVALUATION OF U$sup 233$ FISSION YIELD DATA

Description: A survey of the pertinent literature was made to ascertain the status of data on U/sup 233/ fission-product yields. The various experimental determinations were evaluated, and the most recent mass-spectrometric results were used as a basis for deriving a set of preferred yields. These yields were compared with values reported in two other recent compilations, and for yields >1%, the three setrs agreed with each other to an average precision of <5%. It was concluded that recent measurements have… more
Date: July 13, 1962
Creator: Ferguson, R.L. & O'Kelley, G.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HOMOGENIZATION OF MOLTEN-SALT REACTOR PROJECT FUEL SAMPLES

Description: A copper pulverizer-mixer was designed for homogenizing Molten-Salt Reactor Project (MSRP) fuel. The copper sampling ladle that contains the solidified fuel is placed in the pulverizer-mixer, which is agitated on a mixer mill. The fuel is fractured out of the ladle, pulverized into a homogeneous powder, and transferred to a storage bottle. The homogenized fuel sample is then available for analysis. (auth)
Date: July 1, 1962
Creator: Gaitanis, M.J.; Lamb, C.E. & Corbin, L.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE EXPERIMENTAL DESIGN FOR BeO IRAADIATION EXPERIMENTS ORNL 41-8 AND ORNL 41-9

Description: The experimental plan for irradiating BeO pellets in Experiments ORNL 41- 8 and ORNL 41-9 was chosen in accordance with the principles of experimental design. The design is known by statisticians as a 2/sup 5/ factorial experiment confound'' in six replications. Five variables---size, density, grain size, temperature and time--are controlled at two levels to form the basic 2i factorial experiment. The sixth variable, neutron flux, is introduced by confounding on higher-order interactions. An ex… more
Date: July 18, 1962
Creator: Gardiner, D.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tests of Bearing Materials for the Experimental Through-Tubes in the Egcr

Description: The four experimental through-tubes provided in the Experimental Gas Cooled Reactor will extend directly through the core of the reactor and penetrate both the upper and lower pressure vessel heads. Each tube is anchored in an upper head nozzle and the bottom end is allowed to slide in a lower head nozzle. This lower nozzle is basically a T'' section that provides bottom access to the through-tube and a side access for the piping which connects the throughtube to the experimenter's cell. Due to… more
Date: July 16, 1962
Creator: MacPherson, R. E. & Smith, A. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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