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Aerodynamic Re-Entry Analysis. Task 2. Thermoelectric Generator Summary Report (open access)

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
Radioactive Waste Disposal System Periodic Radiation Monitoring Survey. Core I, Seed 1. Test Results (T-612075). Section 2 (open access)

Radioactive Waste Disposal System Periodic Radiation Monitoring Survey. Core I, Seed 1. Test Results (T-612075). Section 2

Radiation levels were determined at all permanently installed monitored points in the disposal area. Radiation levels were found to be generally higher than those measured during the previous test but within Health Physics limitations. (J.R.D.)
Date: October 1, 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Gaseous Diffusion at Moderate Flow Rates in Circular Conduits (open access)

Gaseous Diffusion at Moderate Flow Rates in Circular Conduits

None
Date: July 1, 1960
Creator: Roley, G. & Fahien, R. W.
Object Type: Report
System: The UNT Digital Library
Nuclear Battery-Thermocouple Type Summary Report (open access)

Nuclear Battery-Thermocouple Type Summary Report

The potential usefulness of approximately 1300 radioactive isotopes as a heat source for the thermoelectric generator was investigated. Only 47 were found to have the proper characteristics of high specific activity and usable haif-life combined with an easily absorbable radiation. These isotopes are discussed showing possible sources of supply, the hazards involved, and the expected performance. Three large Po/sup 210/ heat sources were designed and constructed (for battery use), including one for the SNAP III generator. One small Tl/sup 204/ test heat source was made by irradiation. Eight thermoelectric generators were developed and two of these were used as thermoelectric batteries. Theoretical equations for non-semiconductor thermoelectric materials and experimental measurements to verify the Thompson and Peltier effects are given. (auth)
Date: October 1, 1960
Creator: Blanke, B. C.; Birden, J. H.; Jordan, K. C. & Murphy, E. L.
Object Type: Report
System: The UNT Digital Library
Mass Transfer Coefficients and Interfacial Area in a One Stage Pulse Column (open access)

Mass Transfer Coefficients and Interfacial Area in a One Stage Pulse Column

Over-all mass transfer coefficients were determined independently of the interfacial area by considering the operation of the pulse column to be a stage- wise process. The calculated coefficients describe only the operation of the pulse column for the free rise of organic droplets through a stage, since in the downstroke the aqueous phase passes through the organic phase in the form of rivulets preferentially wetting the plates. The driving force for transfer was based on the aqueous phase concentrations. The mass transfer coefficient was found to increase when the interfacial tension was reduced. Two factors appear to affect the mass transfer coefficient as the pulse frequency is changed and are: a) recycle or backmixing which tends to decrease the coefficient through a reduction of acetic acid in both phases and thereby increases the interfacial tension, and b) turbulence which enhances the coefficient by reducing the continuous film resistance. The first is important at or near the lower flooding limit, but the latter is the controlling factor at higher frequencies. (D.L.C.)
Date: November 1, 1960
Creator: Konopik, A. E. & Burkhart, L.
Object Type: Report
System: The UNT Digital Library
Determination of Aerodynamic Drag Parameters of Small Irregular Objects by Means of Drop Tests (open access)

Determination of Aerodynamic Drag Parameters of Small Irregular Objects by Means of Drop Tests

Drag coefficients were determined for various irregular objects such as glass fragments, stones, steel fragments, and spheres by means of drop tests for use in a mathematical model to correlate nuclear explosion blast experiments. Drop tests were also made on small laboratory animals and extrapolated to estimate the drag properties of man. A method was developed to estimate the average drag properties of man from his total surface area. (D.L.C.)
Date: June 1, 1960
Creator: Fletcher, E. R.; Albright, R. W.; Goldizen, V. C. & Bowen, I. G.
Object Type: Report
System: The UNT Digital Library
Spectrophotometric studies of solutions at elevated temperatures and pressures: status and program for FY1961 and part of FY 1962 (open access)

Spectrophotometric studies of solutions at elevated temperatures and pressures: status and program for FY1961 and part of FY 1962

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.
Object Type: Report
System: The UNT Digital Library
DETERMINATION OF COEFFICIENTS OF REACTIVITY 5532.3 EFPH. CORE I, SEED 1. Test Results (T-550132). Section 1 (open access)

DETERMINATION OF COEFFICIENTS OF REACTIVITY 5532.3 EFPH. CORE I, SEED 1. Test Results (T-550132). Section 1

None
Date: October 17, 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Methods and Techniques of Fallout Studies Using a Particulate Simulant (open access)

Methods and Techniques of Fallout Studies Using a Particulate Simulant

The fallout hazard and protection factors in current use for large groups of buildings, i.e., urban residential areas, business districts, industrial complexes, government centers, Atomic Energy Commission facilities, and academic and medical institutions, are largely unsubstantiated by experimental evidence. These data are important for personnel protection on a national basis in the event of war and on a local basis in the event of certain types of nuclear accidents. The need for such information is discussed and methods for obtaining it are suggested. The methods suggested should provide a cross check of the data obtained on isolated structures under actual fallout conditions with the data from studies that made use of methods such as distributed point sources and a moving single-point source (as used in the Mobile Radiological Measurement Unit, Civil Effects Test Operations) to simulate actual fallout fields and with data from other studies in which predicted values of fallout protection were calculated from strictiy theoretical considerations. (auth)
Date: August 1, 1960
Creator: Lee, W. & Borella, H.M.
Object Type: Report
System: The UNT Digital Library
Zero Field Magnetic Properties of Gadolinium Terbium, and Samarium (open access)

Zero Field Magnetic Properties of Gadolinium Terbium, and Samarium

The mutual inductance or apparent susceptibility due to the presence of the sample in a coaxial inductance coil was observed for Gd, Tb, and Sm in fields of a few gauss over the respective temperature ranges of 78 to 310 deg K, 78 to 235 deg K, and 4.2 to 150 deg K. A paramagnetic Curie point of 284.2 deg K was found for Gd. For Tb, a transition was found which occurred to within 1 deg of the predicted temperature of 220 deg K, and a second peak occurred at 229.4 deg K which is within 2 deg of the heat capacity peak. The 220 deg K peak exhibited hysteresis and time dependence. Extrapolation of Tb data to DELTA M = 0 yielded a Curie point of 235.6 deg K. No hysteresis was observed in the 14.8 deg K peak for Sm. (D.L.C.)
Date: November 1, 1960
Creator: Hill, E. D. & Spedding, F. H.
Object Type: Report
System: The UNT Digital Library
Thermal Expansion and Phase Inversion of Rare-Earth Oxides (open access)

Thermal Expansion and Phase Inversion of Rare-Earth Oxides

Thermal expansion and phase inversion measurements are reported on oxides of Sc, Y, La, and 12 lanthanide series elements up to 1350 deg C. (J.R.D.)
Date: October 1, 1960
Creator: Stecura, S. & Campbell, W.J.
Object Type: Report
System: The UNT Digital Library
Research and Development of Metal Hydrides. Summary Report for October 1, 1958-September 30, 1960 (open access)

Research and Development of Metal Hydrides. Summary Report for October 1, 1958-September 30, 1960

A detailed study of the fundamental relations in the zirconium -- hydrogen system was made in order to clarify the many points of dispute and to evolve a complete picture describing all phases of this system. An engineering evaluation was made of means for utillzing the various high cross-section metal hydrides in shielding or control applications. These materials would combine the processes of thermalization and absorption. Consequently, they are of considerable interest for use in shielding or controlling epithermal reactors. (auth)
Date: November 1, 1960
Creator: Beck, R. L.
Object Type: Report
System: The UNT Digital Library
RADIOLOGICAL HAZARDS FROM RUPTURE OF THE SECONDARY COOLANT SYSTEM OF THE 10 Mw ESCR (open access)

RADIOLOGICAL HAZARDS FROM RUPTURE OF THE SECONDARY COOLANT SYSTEM OF THE 10 Mw ESCR

The hazards study was made to determine the radiation level from the secondary sodium lines of the l0-Mw ESCR, and to evaluate the corresponding radioactive concentration in the secondary loop and the maximum permissible effective activation flux in the intermediate heat exchanger. The results are presented graphicallyn the radiation level from the coolant lines during normal operation as a function of line diameter and Na/sup 4/ concentration; the effective thermal neutron activation flux level in the intermediate heat exchanger as a function of the Na/sup 4/ concentration in the secondary loop and the ratio of the time spent in the flux field to the time spent in making one cycle; average Na concentration in the reactor room atmosphere for operative and inoperative ventilation systems, assuming that all the sodium in the secondary system is released to the room and burns; and the downwind concentration of Na/ sup 24/ resulting from the release of all the secondary sodium on an open pad area exterior to the reactor building. An analysis of the results shows that in the event of an accident the toxicological hazards are more severe than the radiological hazards. Recommendations are given for minimizing the toxological hazards. (B.O.G.)
Date: January 19, 1960
Creator: Piccot, A.R.
Object Type: Report
System: The UNT Digital Library
Equilibrium of the System Lanthanum Nitrate-Praseodymium Nitrate-Nitric Acid-Water-Tributyl Phosphate (open access)