Partner
Oklahoma Historical Society
746
UNT Libraries Special Collections
354
UNT Libraries Government Documents Department
208
Rosenberg Library
132
Hardin-Simmons University Library
35
Abilene Public Library
31
Hopkins County Genealogical Society
31
Sterling Municipal Library
31
Oklahoma Conservation Historical Society
30
Denton Public Library
27
123 More
Collection
Texas Digital Newspaper Program
785
Oklahoma Publishing Company Photography Collection
525
Tocker Foundation Grant
353
Oklahoma Digital Newspaper Program
225
KXAS-NBC 5 News Collection
191
University Photography Collection
140
Harris and Eliza Kempner
132
Office of Scientific & Technical Information Technical Reports
115
Abilene Library Consortium
99
Ladd & Katherine Hancher Library Foundation
88
183 More
States
Decade
Year
Month
Language
2,368 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
2,368
next
THE DEVELOPMENT OF A SUMP-TYPE SOLIDIFIED-METAL SEAL
A solidified-metal seal for possible use in moIten-saIt systems was fabricated and tested on a laboratory scale/su The seal consisted of an 80 Au-20 Cu (wt%) sealant alloy in contact with IN0R-8 base metal/su Eleven successive helium-leak-tlght sealings were effected before termination of the test due to a leak in one of the mating parts/su With better control over the heating cycle and slight modifications in seal design, it is expected that the useful life of a seal of this type could be extended even further. (auth)
Date:
March 15, 1962
Creator:
Donnelly, R.G.
Object Type:
Report
System:
The UNT Digital Library
Criteria for the Design of the Thorium Fuel Cycle Development Facility
Criteria for the conceptual design of the proposed Thorium Fuel Cycle Development Facility to be located at the Oak Ridge National Laboratory were established and are presented. In addition, conceptual layouts of the building and equipment are included. Reference fuel elements and processes that were selected as a basis for developing criteria for the facility are described. (auth)
Date:
March 1, 1962
Creator:
Irvine, A.R. & Lotts, A.L.
Object Type:
Report
System:
The UNT Digital Library
Emission Characteristics of Tantalum, Tungsten, Rhenium, and Iridium in Plasma Diodes
Experimental determinations of the ionic and electronic emission characteristics of Ta, W, Re, and lr cathodes in vapor thermionic converters are compared. It is shown that Ta provides superior thermal ionization qualities at high pressure compared with W, Re, and Lr. High electronic current densities may be obtained from Cs on Re and Cs on Ir at much lower Cs vapor pressures than from Ta or W. An over-all efficiency of 19% was achieved with a Re cathode at 2440 deg K. (auth)
Date:
March 15, 1962
Creator:
Gust, W. H.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Heat Rejection Systems for PL-3
An investigation was made of heat rejection systems for use in the PL-3 nuclear power plant, designed for placement at Byrd Station, Antarctica. It was concluded that the glycol-coupled surface condenser and air blast cooler combination appears to be suited for PL-3 plant requirements and operating conditions. (auth)
Date:
March 1, 1962
Creator:
Thurnau, C. J.
Object Type:
Report
System:
The UNT Digital Library
Spent Fuel Transfer, Storage and Shipment for PL-3
In refueling development studies performed on PL-3 Phase I design, several methods of fuel transfer, storage, and shipment were investigated. An evaluation of the relative merits of the systems and designs under study, as applied to either the BWR or PWR concepts, is made and optimum designs are selected. An analysis of spent fuel shipping cask shielding requirements is presented, along with recommendations for future study in this area. (auth)
Date:
March 1, 1962
Creator:
Hauenstein, G. C. & Pomeroy, D. L.
Object Type:
Report
System:
The UNT Digital Library
Research in Radiobiology. Annual Report of Work in Progress on the Chronic Toxicity Program
Separate abstracts were prepared on 8 sections of this report. Data are also included on the status of dogs at various time intervals following the injection of various doses of Ra/sup 226/, Pu/sup 239/, Ra/sup 228/, Th/sup 228, and Sr/sup 90/. (C. H.)
Date:
March 31, 1962
Creator:
Dougherty, T. F.
Object Type:
Report
System:
The UNT Digital Library
Multigroup Calculations of Effective Delayed-Neutron Fractions, Prompt- Neutron Lifetime, and Related Kinetics Parameters. IBM-704 Program 1188/RE
In the course of a recent study of kinetics parameters, it was found that RE-185, because of its limitations, was inadequate to handle the problems involved with the reactors considered. Program ll88/RE was written entirely independent of and is intended to make RE-185 obsolete. The multigroup calculations of primary interest performed by the code are as follows: the total effective delayed-neutron fraction and its distribution into six ' families'' which are characterized by their periods; the prompt-neutron lifetime; and the worth of delayed and prompt neutrons in the core and blanket regions for all fissionable materials. Fluxes used in these calculations are taken directly from the real and adjoint solutions as obtained by RE-l22. (auth)
Date:
March 1962
Creator:
Kvitek, L. C.
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
SALT PHASE CHLORINATION OF REACTOR FUELS. IV. NIOBIUM BEHAVIOR IN THE LEAD CHLORIDE AND CHLORINE-LEAD CHLORIDE SYSTEMS
Investigation of the behavior of Nb in PbCl/sub 2/ showed that the Nb dissolution rate is quite low. Since stirring increases the rate appreciably, it is likely that the initial reaction is diffusion controlled. A subsequent reaction is linear in rate with an activation energy of 23.4 kcal per mole. Incomplete volatilization of dissolved Nb from PbCl/sub 2/ is due to the presence of lower oxidation states of Nb. The addition of Cl to PbCl/sub 2/ increases the rate of dissolution of Nb. The rate is high enough at reasonable temperatures to be practical for fuel dissolution, e.g. 12 mg min/sup -1/ cm/sup -2/ at 550 deg C and 120 mg min/sup -1/ Cl. Volatilization of NbCl/sub 5/ is 99.9% complete at 550 deg C. (auth)
Date:
March 15, 1962
Creator:
Teague, J. L.; Hahn, H. T. & Vander Wall, E. M.
Object Type:
Report
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
GUIDE TO NUCLEAR POWER COST EVALUATION. VOLUME 4. FUEL CYCLE COSTS
Information on fuel cycle cost is presented. Topics covered include: nuclear fuel, fuel management, fuel cost, fissionable material cost, use charge, conversion and fabrication costs, processing cost, and shipping cost. (M.C.G.)
Date:
March 15, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
EGCR EXPERIMENTAL LOOPS, PRELIMINARY DESIGN REPORT
The EGCR was designed to accommodate up to four gascooled experimental loops plus several experimental fuel elements in the open core. Two of the loops will utilize 51/2-in.-O.D. stainless steel tubes passing through the core along an axis which is about 17 in. from the central axis of the core. The other two loops will utilize 91/2-in.-o.d. tubes about 68 in. from the central axis. Inherent safety in the design, facility design, primary loop design, auxiliary systems and equipment design, primary and secondary containment design, instrumentation and controls, and special operations are discussed. (M.C.G.)
Date:
March 27, 1962
Creator:
Neill, F.H. & Michelson, C.
Object Type:
Report
System:
The UNT Digital Library
STATUS REPORT ON LAMB WAVES
Theoretical and experimental aspects of Lamb waves are considered. These are described as body waves, or modes, which travel throughout an entire plate and are radiated from both surfaces, so that it is possible to detect Lamb waves when the receiver and sender are on opposite sides of the plate. Studies concerning applications of Lamb waves are reported in the field of nondestructive testing. (J.R.D.)
Date:
March 1, 1962
Creator:
di Novi, R.A.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Status Report on LAMPRE Program for Period Ending February 20, 1962
BS>LAMPRE I. The reactor operation is discussed. A malfunction in the shim operation was found and corrective measures taken. The core reloadings and other reactor modifications are described. The results of a gamma scanning of a fuel capsule are given. Fuel and Container Development. The properties and behavior of the Core I and the materials developed for Core II are described. Corrosion tests were carried out on pure Ta containers with molten Pu-Ce-Co alloys at 750 to 900 deg C, and the results indicate that Pu-Ce-Co alloys containing less than 5 g/cm/sup 3/ Pu should be acceptable for use in LAMPRE. The crystal structures of Pu/sub 3/Co and the most Ce-rich compound in the Ce-Co system, Ce/sub 24/Co/sub 11/, were determined. Results are given for a search for ternary eutectic alloys of high U content and for an investigation of the eutectic temperatures of several binary U alloys. Corrosive tests on ceramic materials with molten Mn-Pu-U and Mn-U alloys at 900 to 1000 deg C are summarized. Critical Experiments. Specifications and status are given for PBX. Core Test Facility. The status of the Core Test Facility design is given. The sodium systems, heat dump system, and disassembly cell mockup are …
Date:
March 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
LABORATORY PROGRESS ON THE DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE BY DEEP- WELL INJECTION
Results of laboratory studies on the neutralization of Purex-type wastes are reported, including the radiochemical distribution of the fission products in the precipitate and supernate and the effect of sodium and calcium neutralizations on fission-produet separation. The problem of interstitial precipitation encountered when a second incompatible liquid is injected into a formation is discussed. Results indicate a piston-iike displacement of the interstitial liquid by the injected waste with only a small zone of precipitation formed along the contacting edge. Slurry tests were performed to determine the eapacity of various geologic materials for sorption of cesium and strontium from a synthetic Purex-type waste containing carriers and tracers. The materials studied include sands, feldspars, shales, clays, and limestone. The amount of cesium sorbed was found to be a function of several variables, among which are concentration of cesium in the waste, concentration of other cations, amount and nature of the clay material, and composition and amounts of other minerals in the disposal formation. Several types of shales and clay minerals, including illite, bentonite, montmorillonite, kaolinite, halloysite, and Conasauga shale, were slurried with simulated neutralized 6 M Purex waste. Sorption of cesium ranged from 0.6 to 6.0 mg/20 g, respectively, for the various …
Date:
March 1, 1962
Creator:
Lacy, W.J.; Sealand, O.M.; Jacobs, D.G. & Struxness, E.G.
Object Type:
Report
System:
The UNT Digital Library
MANY-BODY THEORY (Based on a series of lectures given by J.R. Schrieffer)
ABS>Notes from a series of l5 lectures on many-body theory given at Argomme Nationaf Laboratory in the spring of 1961 are presented. Topics covered include: formalism of quantum field theory, Heisenberg and interaction representations, Green's functions in the many-body problem, perturbation expansion for Green's functions, high-density electron gas, and theory of superconductivity. (M.C.G.)
Date:
March 1, 1962
Creator:
Bassani, F. & Robinson, J.
Object Type:
Report
System:
The UNT Digital Library
THE DESIGN AND CONSTRUCTION OF THERMAL FLOWMETERS
A thermal flowmeter was designed and tested which will measure a wide range of flow rates for highly corrosive gases. Response to flow rate changes is fast. The pararaeters for changing the size and response to the flowmeter were evaluated. (auth)
Date:
March 1, 1962
Creator:
Kessie, R.W.
Object Type:
Report
System:
The UNT Digital Library
MTR Fast Neutron Flux Measurements for Cycle 146
The fast neutron fluxes in selected positions of the MTR were measured for Cycle 146. The measurements were made at the beginning, throughout, and at the end of the cycle (564 Mwd). Vertical traverses for each position monitors are shown. (auth)
Date:
March 20, 1962
Creator:
Weber, L. D. & Hogg, C. H.
Object Type:
Report
System:
The UNT Digital Library
A STUDY OF LIQUIDS BY NEUTRON SCATTERING
A radial density-distribution function for liquids was derived with the aid of the assumption that vibrational modes exist in liquids. The distribution function was obtained only for elastically scattered neutrons. A study of si(s) curves as a function of temperature, as well as the energy distribution of the scattered neutrons, affords a way in which to construct a model describing the motion of atoms in a liquid. (auth)
Date:
March 1, 1962
Creator:
Persiani, P.J.
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Technology Quarterly Progress Report, October-December 1961
The ICPP processed Al fuel, prtncipally of the MTR-ETR type, durtng this quarter. Newly designed and installed processing equipment exhibited excellent operating performance. This included direct-air-pulsed extraction, stripping and scrub columns, and a cascade-controlled continuous evaporator in first cycle product concentration service. Aqueous zirconium fuel processing studies continued with the objective of adapting the hydrofluoric acid process to continuous dissolution-complexing to increase the capacity of the LCPP process while using as much existing equipment as possible to minimize costs. Six variations of hydrofluoric acid flowsheets were tested in a smallscale continuous dissolvers. Dissolution rates were found to be high in all cases and dissolution was easily initiated at temperatures as low as 36 deg C. Monel and Carpenter 2O(Nb) were found to be satisfactory construction materials, from the standpoint of corroston, if oxidizing conditions were carefully controlled. Additional studies are reported on the stability of blended Zr and Al process raffinates and on the nature of the solids which result from the sodium formate headend precipitation process. Electrolytic dissolution studies, dtrected at fundamentals of current utiltzation in a series''-type dissolver, demonstrated that high current utilization is obtained when the polarization resistance is small compared with the solution resistance. Factors affecting …
Date:
March 28, 1962
Creator:
Bower, J. R.
Object Type:
Report
System:
The UNT Digital Library
ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT
UHTREX utilizes a high-temperature, He-cooled, graphite moderated reactor employing unclad, refractory fuel elements. The reactor is designed to produce a msximum thermal power of 3 Mw and a maximum exit He temperature of 2400 deg F. The purpose of the experimert is to evaluate the advantages of the simple fuel against the disadvantages of the associated operation of a contaminated coolant loop. The mechanical and nuclear design of the reactor and related apparatus are described, discussed, and evaluated from the standpoint of hazards associated with conduct of the experiment. The building design and characteristics of the site are also examined from the same standpoint. The probable effects of operational errors and component failures are studied. The conseqnences of credible accidents are not considered to be catastrophic for either operating personnel or personnel in surrounding areas. (auth)
Date:
March 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
SPECTRAL SHIFT CONTROL REACTOR BASIC PHYSICS PROGRAM-THEORETICAL ANALYSIS. PART I. ANALYSIS OF EXPERIMENTS
The data obtained in the series of SSCR experiments and the theoretical analysis of the results demonstrate the spectral shift control principle clearly. The critical assemblies show that considerably larger amounts of fuel can be loaded into a core moderated with a mixture of D/sub 2/O and H/sub 2/O than in one moderated with H/sub 2/O alone. The measured Cd ratios and the calculated neutron balances show that the excess reactivity associated with this extra mass is held up in the resonance absorption of the fertile material. This leads to a higher conversion ratio system than the same sized lattice controlled by thermal neutron poison. Very good agreement is obtained between experimental and theoretical values for nearly all important parameters over the entire range of D/ sub 2/O concentration in the moderator. This agreement confirms the use of the BPG-four-group treatment, and demonstrates the calculation of reactor criticality and other measured integral parameters from fundamental cross sections without the use of intermediate fitting functions. The reactor leakage part of the calculational model is shown to be accurate by the good agreement obtained between calculated and experimental values of age, criticality, change of criticality with moderator height, and the comparison between …
Date:
March 1, 1962
Creator:
Wehmeyer, D.B.; Doederlein, J.M.; Roach, K.E. & Wittkopf, W.A.
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report, August 1961
Engineering studies of a 6-in.-ID countercurrent foam column were started. The capacity of Mark II Stacked Clone Contactor was found to be limited by gradually increasing entrainment. Thoria sols were prepared from trough denitrator products in a conical bottom tank agitated by circulation through an external centrifugal pump. Experimental results agreed favorably with predicted results for the reaction of CO with CuO and fur the simultaneous reactions of H/ sub 2/ and CO with CuO. In a 2-in. dissolver, Modified Zirflex dissolution rates of Zircaloy-2 increased non-linearly with F/S. The 250-ton prototype shear was received and installed. Priorities were established for development work on graphite fuels. A total of 5 SR Core I fuel clusters were mechanically dejacketed from the second carrier shipment of SRE Core I fuel. Degradation of NaK to a solid or waxy form required that the slugs be ejected by the jackscrew. The NaK disposal system operated satisfactorily for the Iast ~3000 ml of NaK. A procedure for estimating the temperature rise of spent reactor fuels during shipping gives reasonably good results. A puIse column was operated with the light phase c nt-nuous using an external phase separator. Zirconium ates were dissolved by HF in molten …
Date:
March 1, 1962
Creator:
Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type:
Report
System:
The UNT Digital Library
Annual Progress Report on Fuel Element Development for Fiscal Year 1961
Progress in fuels and materials development is summarized. Major areas of investigation include a materials study by means of sample fuel plates containing uranium alloys or cermets, burnable poisons, non-uniform fuel and poison distributions and clad with various aluminum alloys; and an engineering study of fuel element geometries optimized in heat transfer, hydraulics, and materials strength. Up to 45 wt% U-Al alloys, 6 to 65 wt% UO/-Al and U3O6-Al dispersions, including enrichments ranging from 20% to 93%, were tested to 70% burnup in de-ionized water at 200 deg F in the MTR. Their performance at higher temperature is still being investigated. Test results for the MTR conditions indicate that all of the compositions investigated to date will successfully withstand even the longest irradiation at these conditions if properly fabricated. Some high strength aluminum alloy claddings, not yet fully tested, show some peculiar surface effects which may be related to corrosion. Metallographic studies of irradiated cermets reveal a reaction'' (diffusion) zone produced around UO/sub 2/ particles in contact with aluminum. These zones are being studied by means of x-ray diffraction, electron microscopy, and electron microprobe analysis. From engineering studies has come promise of improved heat removal and lower pumping requlrements for …
Date:
March 1, 1962
Creator:
Gibson, G. W. & Shupe, O. K.
Object Type:
Report
System:
The UNT Digital Library