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Magnetic Properties of Insulators. Quarterly Report No. 2 Covering Period May 15, 1961 to August 15, 1961
The electron paramagnetic resonance (EPR) of color centers in additively colored KCl crystals is measured to observe the effects of optical bleaching at room temperature. Earlier measurements on the F-center are confirmed and the susceptibility is measured at 78 and 300 deg K over five decades of power, including the very low power region. The width and the saturation properties of the individual multiplets are studied in detail and the technique of making E PR measurements on inhomogeneously broadened lines is discussed. A calculation is presented which shows that a slight departure from a Lorentzian multiplet shape can account for the saturation data. The bleached crystals show a resonance which has a width of 35 gauss and a different rate of saturation than the F- center. This resonance is associated with the B-band which appears in the optical absorption. (auth)
Date:
August 30, 1961
Creator:
Markham, J. J.
Object Type:
Report
System:
The UNT Digital Library
APPLICATIONS OF SNAP REACTOR SYSTEMS TO COMMUNICATIONS SATELLITES
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.
Object Type:
Report
System:
The UNT Digital Library
PROCESSES FOR RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE FUEL ELEMENTS. PART II
Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel elements are reported. The 90% HNO/sub 3/ process, which involves simultaneous disintegration and leaching in 21 M HNO/sub 3/, is applicable to all fuel elenments which do not contain coated fuel particles. Leaching of irradiated (0.001% burnup) fuels containing 3 and 12% uranlum recovered approximates 99.3 and 99.9%, respectively, of the uranium in two 4-hr leaches with boiling acid. The graphite residue retained > 50% of the long-lived fission products. Three successive leaches of fuel containing uranium and thorium recovered approximates 99% of both elements. Uranium recoveries by combustion in oxygen followed by dissolution of the ash hn nitric acid or fluorlde-catalyzed nitric acid are quantitative only when the fuel is not coated, does not contain Al/sub 2/O/sub 3/-coated fuel particles, and is free from impurities such as iron. During combustion up to 95% of the Ru-106 was volatilized from irradiated specimens. Recoveries, by leaching with 70% HNO/sub 3/, from fuel specimens containing Al/sub 2/O/sub 3/-coated fuel particles were greater than 99% when the specimens were ground finer than 200 mesh to ensure crushing of the fuel particles. (auth)
Date:
November 30, 1961
Creator:
Ferris, L.M.; Kibbey, A.H. & Bradley, M.J.
Object Type:
Report
System:
The UNT Digital Library
STUDIES OF THE SCINTILLATION PROCESS IN CsI(Tl)
The scintillation response of CsI(Tl) crystals, having various thallium contents, was measured for excitation of the crystals by monoenergetic gamma rays, protons, and alpha particles. The investi gation was made to provide a test of some of the features of a theoretical model of the scintillation process in thallium-activated alkali iodides proposed by Murray and Meyer. In order to insure that the results obtained in this program would provide a critical test of the scintillation model, special attention was paid to technical effects which could influence the interpretation of the experimental data. For example, the effect of the pulseanalysis time on the relative scintillation response of CsI(Tl) to various charged parti cles was investigated. In addition, the emission spectra of the CsI(Tl) crystals were measured for excitation by x rays, protons, and alpha particles. The results of the investigation showed that the scintillation efficiency of CsI(Tl) is a continuous function of dE/dx, as assumed in the scintillation model, within the accuracy of the experiments when the effect of delta ravs are considered. This led to the conclusion that the light output of CsI(Tl) crystals is, in general, a nonlinear function of the energy of the particle. The shape of the …
Date:
November 30, 1962
Creator:
Gwin, R. & Murray, R. B.
Object Type:
Report
System:
The UNT Digital Library
Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 2, December 15, 1961 to March 14, 1962
The purpose of this investigation is to determine the extent to which Zr and Zr alloys exhibit delayed failure (static fatigune) as caused by a combination of absorbed H and applied stress. Both notched and unnotched specimens of unalloyed Zr and Zircaloy-2 were hydrogenated to 200 ppm and 500 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture was observed which can be attributed to the delayed failure phenomenon; it appears that these materials are relatively insensitive to static fatigune. The effects of grain size, temperature, cold deformation, and superheated water and steam corrosion on susceptibility to delayed failure are being determined. (auth)
Date:
March 30, 1962
Creator:
Weinstein, D. & Holtz, F. C.
Object Type:
Report
System:
The UNT Digital Library
Pakistan: Situation Report
This report is the situational report of Pakistan which includes its Political Affairs, Economy, and Foreign Relations.
Date:
September 30, 1968
Creator:
Niksch, Larry A.
Object Type:
Report
System:
The UNT Digital Library
[News Script: New Year]
Script from the WBAP-TV/NBC station in Fort Worth, Texas relating a news story.
Date:
December 30, 1968
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Script
System:
The UNT Digital Library
KINETIC EXPERIMENTS ON WATER BOILERS, "A" CORE REPORT. PART I. PROGRAM HISTORY, FACILITY DESCRIPTION, AND EXPERIMENTAL RESULTS
None
Date:
March 30, 1962
Creator:
Flora, J.W.; Gardner, E.L.; Greenfield, M.A.; Roecker, J.H. & Stitt, R.K.
Object Type:
Report
System:
The UNT Digital Library
Periodic Waste Disposal System Material Balance Test. Core 1, Seed 2. Test Evaluation T-641317. Section 1
A test was carried out to determine the adequacy of storage capacity and operating procedures of the radioactive waste disposal system during a normal reactor plant warmup. The capacity and operating procedures were found to be adequate. It was impossible to perform a complete material balance based on existing level instrumentation and using the data required by the test procedure. Approximately 21,290 gal. of waste were received in the system and 13,210 gal. were discharged to the river with a total activity of 1200 mu c. A quantity of 6,670 gal. of reactor coolant effluent was processed. Approximately 634 lb of combustible waste were incinerated. (M.C.G.)
Date:
June 30, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962
S>Progress is reported on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant. The topics covered include: fuel material cladding, bonding, and irradiation testing; heat transfer and fluid flow; fuel element manufacturing research and development; low-enrichment superheater fuel element design; mechanical studies of control rods, guide tubes, and control rod drives; reactor physics; and reactor and system dynamics. (C.H.)
Date:
June 30, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
PL FINAL DESIGN REPORT. VOLUME II. PLANT DRAWINGS
Plant drawings for the final design for the Army Reactor (PL-2) are presented. Two hundred and twenty-eight figures are included. (M.C.G.)
Date:
June 30, 1961
Creator:
Combustion Engineering, Inc. Nuclear Div., Windsor, Conn.
Object Type:
Report
System:
The UNT Digital Library
Research and Development Reports for Sodium to Sodium Intermediate Heat Exchanger and Sodium to Water Steam Generator
Results are presented of research and development work performed in conjunction with the 70-Mw design of a sodium-to- sodium intermediate heat exchanger and a sodium-to-water steam generator. Kanigen plating was substituted for Inconel overlays. A program to evaluate this plating was undertaken. Elimination of tube end ferrules, mechanical behavior of sine wave tubes, tube-to- tube sheet welded connections, metallurgical examination of bimetallic tubes, transition weld test, bayonet tube test, and bayonet tube weld cap test are discussed. (M.C.G.)
Date:
October 30, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
REACTOR FUEL WASTE DISPOSAL PROJECT-PERMEABILITY OF ROCK SALT AND CREEP OF UNDERGROUND SALT CAVITIES. Final Report
A study was made of two problems of salt-cavity storage, namely, seepage of wastes out of formations and closure of cavities due to plastic flow of salt. The results indicate that both problems are negligible; bedded salt is more impermeable than dome salt. Kerosene was found to be nonreactive with dome salt whereas brine solutions showed some interaction. It is concluded that storage of radioactive wastes in salt cavities is feasible. (D.L.C.)
Date:
December 30, 1960
Creator:
Reynolds, T.D. & Gloyna, E.F.
Object Type:
Report
System:
The UNT Digital Library
FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Final Report
>The basic fuel element consisted of a uniform dispersion of fuel in a 1 1/2 inch diameter graphite sphere. Ceramic coatings for the retention of fission products were studied. It was found-that molecularly deposited'' ceramics such as alumina, siliconized silicon carbide, and pyrolytic carbon were excellent barriers to fission product leakage. The most advantageous location for ceramic coatings was found to be on the individual fuel particles, where the coating was subject to smaller forces and where a larger thickness-todiameter ratio could be used than if the coating were on the surface of the graphite sphere. Fuel elements were irradiated to burnups ranging up to about 6 at.% U/sup 235/. In all specimens containing a uniform dispersion of fuel, the graphite spheres were found to retain their structural properties after irradiation. Data are given on fuel particle coatings of A1/sub 2/O/sub 3/, pyrolytic carbon, and metals: surface coatings of siliconized silicon carbide, pyrolytic carbon, and metal carbides; properties of and the effects of irradiation on graphite spheres; the use of natural graphite in preparing a high-density matrix material; graphite fueling by thorium nitrate infiltration; subsurface metal and metal carbide coatings for graphite; and an in-pile loop program on the behavior …
Date:
April 30, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
PROGRAM ODD--A ONE-DIMENSIONAL MULTIGROUP CODE FOR THE IBM-7090 (ANP PROGRAM NO. 657)
The physical and mathematical reactor models which are used in Program ODD are discussed. In addition, the FORTRAN II source program listings, decimal data input sheets, and input and output for a sample case are given. Program ODD was designed to raake use of the Revised Nuclear Data System at ANPD which consists of twenty-five energy group cross-section data including high energy inelastic scattering matrices, resonance parameters for the resolved resonances, and thermalization scattering matrices for the near thermal energy region. The most unique aspect of the program is the mathematical technique employed for eliminating inner iterations and slow convergenc rates occasioned by the up- scattering'' in the thermalization region of the energy lattice. Direct inversion of the energy matrix coupling the thermal and last four epitherma groups provides simultaneous consistent solutions for thes groups within each power iteration. (auth)
Date:
June 30, 1961
Creator:
Fischer, P.G.; Wenstrup, F.D. & Hoffman, T.A.
Object Type:
Report
System:
The UNT Digital Library
Analysis of the Initial Nuclear Superheat Critical Experiments. Supplementary Study Related to Bonus and Nuclear Superheat Programs
A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boilersuperheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods used in the study predict the measured reactivity and power distribution to within the limits of experimental accuracy. (T.F.H.)
Date:
January 30, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
[News Clip: Race]
Video footage from the WBAP-TV station in Fort Worth, Texas to accompany a story about the Worth Theatre hosting live television coverage of the Indianapolis 500 with more than two thousand fans watching the closed-circuit telecast.
Date:
May 30, 1964
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Video
System:
The UNT Digital Library
[News Clip: Demonstrators]
Video footage from the WBAP-TV television station in Fort Worth, Texas, covering a news story about a civil rights demonstration at the Dallas Piccadilly Cafeteria.
Date:
May 30, 1964
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Video
System:
The UNT Digital Library
[News Clip: Jacksboro stuff]
Video footage from the WBAP-TV station in Fort Worth, Texas to accompany a story about the first annual Fort Richardson Frontier Day sponsored by the Jack County Historical Society in Jacksboro, Texas.
Date:
May 30, 1964
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Video
System:
The UNT Digital Library
[News Clip: Smile]
Video footage from the WBAP-TV station in Fort Worth, Texas to accompany a story about Lynn Doyle of Italy, Texas winning the Smile Girl beauty contest held at the Titche-Goettinger department store in Dallas.
Date:
May 30, 1964
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Video
System:
The UNT Digital Library
[News Clip: Buildings]
Video footage from the WBAP-TV station in Fort Worth, Texas to accompany a story about W. T. Overton's plans for a construction project in downtown Dallas, Texas.
Date:
May 30, 1964
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Video
System:
The UNT Digital Library
Stress Analysis of the SM-1A Reactor Vessel
The stress analysis performed on the SM-lA reactor vessel and cover is presented. The msximum combined stress (51,360 psi in compression) occurs in the vessel cover during a 50 deg F/hr transient. A fatigue analysis of these stresses indicated that they could be applied safely at least 2500 times, and since the vessel is expected to receive less than 900 cycles, it should not suffer any fatigue damage. (auth)
Date:
March 30, 1962
Creator:
McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A. & Aitken, C. C.
Object Type:
Report
System:
The UNT Digital Library
PL FINAL DESIGN REPORT. VOLUME V. CORE DRAWINGS AND SPECIFICATIONS
Drawings andd specifications for the PL reactor core are given. The requirements for the material procurement, fabrication, testing, and inspection of one P L-2 reactor core and spares are listed. (M.C.G.)
Date:
June 30, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
MARITIME GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING, SEPTEMBER 30, 1960
The feasibility was studied and a cost estimate prepared of an experimental reactor to determine the operating characteristics of beryllia- moderated, gas-cooled systems wtthin a power limit of 10 Mw(t). The heat energy produced by the experimental reactor is to be dissipated in a heat dump. No machinery for production of power was to be provided. Other requirements were that the reactor should be capable of testing core types different from the current MGCR design, and the system should permit use of gases other than helium. It was further directed that the reactor should be designated BORE for Beryllium- Oxide Reactor Experiment. Reactor development work was mainly in connection with the BORE preliminary design. It was established that the most important information which could be provided by a 10 Mw(t) reactor experiment would be on performance of fuel elements and moderator bodies. This required that the experirment duplicate the power density in the fuel and moderator that would exist in the full size reactor and made it advisable to use full length fuel elements. This resulted in an unconventionally shaped core which is roughly cylindrical with the length more than twice its mean diameter. Studies continued on performance of fuel …
Date:
September 30, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library