Partner
Oklahoma Historical Society
779
UNT Libraries Special Collections
468
UNT Libraries Government Documents Department
367
Texas Historical Commission
52
Dublin Public Library
28
Sterling Municipal Library
25
Brownwood Public Library
24
UNT Libraries
21
Carl Albert Congressional Research and Studies Center
20
Deaf Smith County Library
20
100 More
Collection
Oklahoma Publishing Company Photography Collection
556
Texas Digital Newspaper Program
464
KXAS-NBC 5 News Collection
360
Office of Scientific & Technical Information Technical Reports
301
Oklahoma Digital Newspaper Program
247
Tocker Foundation Grant
211
University Photography Collection
85
THC Historic Resources Survey Collection
48
Abilene Library Consortium
40
The Oklahoma City Times
39
158 More
Country
States
Year
Month
Energy-averaged neutron cross sections of fast-reactor structural materials
The status of energy-averaged cross sections of fast-reactor structural materials is outlined with emphasis on U.S. data programs in the neutron-energy range 1-10 MeV. Areas of outstanding accomplishment and significant uncertainty are noted with recommendations for future efforts. Attention is primarily given to the main constituents of stainless steel (e.g., Fe, Ni, and Cr) and, secondarily, to alternate structural materials (e.g., V, Ti, Nb, Mo, Zr). Generally, the mass regions of interest are A approximately 50 to 60 and A approximately 90 to 100. Neutron total and elastic-scattering cross sections are discussed with the implication on the non-elastic-cross sections. Cross sections governing discrete-inelastic-neutron-energy transfers are examined in detail. Cross sections for the reactions (n;p), (n;n',p), (n;..cap alpha..), (n;n',..cap alpha..) and (n;2n') are reviewed in the context of fast-reactor performance and/or diagnostics. The primary orientation of the discussion is experimental with some additional attention to the applications of theory, the problems of evaluation and the data sensitivity of representative fast-reactor systems.
Date:
February 1, 1978
Creator:
Smith, A.; McKnight, R. & Smith, D.
Object Type:
Article
System:
The UNT Digital Library
Effects of atmospheric variability on energy utilization and conservation. Final report, 1 November 1976--31 October 1977
A space-heating energy-consumption model for Greeley, Colorado for the winter of 1976-77 was within 98.9 percent of actual natural gas consumption for that city. Modeling of Cheyenne, Wyoming, including the testing of a new statistical scheme to develop the building census required by the energy consumption model, has progressed to the point where reliable natural gas consumption estimates can be made with the model for that community. A detailed study of temperature and surface wind patterns in and near the city of Greeley, Colorado revealed that, at times, an urban heat island effect is present, in spite of the relatively small size of that town. Various feedback mechanisms between the oceans and the atmosphere were examined. Several of these mechanisms appear to be the cause of the interannual variability of the atmosphere's general circulation and of climatic changes on a time scale of several tens of years. A recent cooling trend in the North Pacific north of 40/sup 0/N, and sea-surface temperature fluctuations with an irregular periodicity of 2 to 4 years superimposed upon this trend were studied. To advance regional long-range forecasting skills January temperature anomalies over the eastern United States were correlated with flow patterns over the U.S. …
Date:
February 1978
Creator:
Reiter, Elmar R.; Dreiseitl, E.; Johnson, G. R.; Leong, H. H.; Macdonald, B. C.; Somervell, W. L. Jr. et al.
Object Type:
Report
System:
The UNT Digital Library
Proposal for study of vacuum adiabatic compression of relativistic electron beam generated by a foilless diode. [5 to 50 MeV]
A theoretical investigation to study the generation of an intense relativistic electron beam by a foilless diode and subsequent adiabatic compression is proposed. 2 figures, 1 table, 39 references.
Date:
February 1, 1978
Creator:
Thode, L.E.
Object Type:
Report
System:
The UNT Digital Library
January 1978 monthly highlights for Office of Nuclear Regulatory Research Programs at Oak Ridge National Laboratory
Highlights of technical progress during January 1978 are presented for sixteen separate program activities which comprise the ORNL research program for the Office of Nuclear Regulatory Research's Division of Reactor Safety Research.
Date:
February 10, 1978
Creator:
Mynatt, F.R. (comp.)
Object Type:
Report
System:
The UNT Digital Library
Review of issues relevant to acceptable risk criteria for nuclear waste management
Development of acceptable risk criteria for nuclear waste management requires the translation of publicly determined goals and objectives into definitive issues which, in turn, require resolution. Since these issues are largely of a subjective nature, they cannot be resolved by technological methods. Development of acceptable risk criteria might best be accomplished by application of a systematic methodology for the optimal implementation of subjective values. Multi-attribute decision analysis is well suited for this purpose.
Date:
February 22, 1978
Creator:
Cohen, J.J.
Object Type:
Article
System:
The UNT Digital Library
Electrode polarization studies in hot corrosion systems. Progress report, June 1, 1977--May 31, 1978
Analysis of thermodynamic models pertaining to coal gasification is near completion. Model I, comprising a gas phase and a molten salt phase, pertains to laboratory materials testing; Model II incorporates as well a solid carbon phase and is intended to model typical gasifier environments. Anodic and cathodic polarization measurements on iron, 1018 steel, nickel, and 304 and 316 stainless steel have been performed in molten sodium carbonate under air and oxygen; tests under reducing environment are in progress. Preliminary metal/gas reactions tests involving iron, and hydrogen sulfide and nitrogen, have been performed. Reaction with nitrogen is minimal; reaction with hydrogen sulfide is very non-uniform, rendering kinetic analysis difficult.
Date:
February 1, 1978
Creator:
Devereux, O.F.
Object Type:
Report
System:
The UNT Digital Library
Coal Technology Program. Progress report for December 1977
In the pressure vessel and piping materials work, the report, ''Assessment of Materials Technology for Gasifer and Reaction Pressure Vessels and Piping for Second Generation Commercial Coal Conversion Systems'' (ORNL-5238), has been submitted for publication and distribution. Impact and tensile teting is under way on 2/sup 1///sub 4/ cr-1 Mo steel which has received a simulated quench, temper, and postweld heat treatment. Two topical reports on coating inspection have gone to reproduction. CoCrAlY material has been received and specimen production has been initiated. We are streamlining our methods for eddy-current design and have developed a new method for material characterization. A penetrant procedure for cermet coatings has been optimized and some interesting observations of coating behavior were made during the tensile cracking of a cermet specimen. In the welding and cladding program, experimental gas metal-arc weld-clad depits of type 320 Cb stainless steel have been made on an intermediate layer of Inconel 82 (primary substrate material is steel). Metallographic and micoprobe examination of tubes from the 1500-hr FluiDyne AFBC fireside corrosion test showed mild oxidation on both the ID and OD, no indication of sulfidation attack, and very slight intergranula corrosion. Examination of various valve components and air distributor plates …
Date:
February 1, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Summary of beryllium specifications
This report summarizes and compares the main beryllium properties included in producer, Department of Energy (formerly ERDA) facility, and government specifications. These data are tabulated in a sequence established primarily by increasing purity and secondarily by increasing tensile properties. Comments on formability and weldability are also included.
Date:
February 17, 1978
Creator:
Corle, R. R.
Object Type:
Report
System:
The UNT Digital Library
Investigative study of engine limiting
An experimental study was conducted to determine the effect of cylinder cut-out or ''engine limiting'' on fuel consumption and exhaust emissions for a current technology V-type 8-cylinder engine. Increases in energy conversion efficiency while operating with only 4 cylinders ranged from 10 to 40% compared to operation with 8 cylinders at the same power outputs. The speeds and loads chosen were representative of those required to operate a 4,500-lb vehicle at speeds up to 60 mph. Hydrocarbon emissions increased at low speed/load points under 4 cylinder operation. An insignificant change in carbon monoxide emissions was observed while an increase in oxides of nitrogen emissions resulted at the higher speed/load points.
Date:
February 1, 1978
Creator:
Bechtold, R.L.
Object Type:
Report
System:
The UNT Digital Library
Procedure for the analysis of americium in complex matrices
A radioanalytical procedure for the analysis of americium in complex matrices has been developed. Clean separations of americium can be obtained from up to 100 g of sample ash, regardless of the starting material. The ability to analyze large masses of material provides the increased sensitivity necessary to detect americium in many environmental samples. The procedure adequately decontaminates from rare earth elements and natural radioactive nuclides that interfere with the alpha spectrometric measurements.
Date:
February 1, 1978
Creator:
Knab, D.
Object Type:
Report
System:
The UNT Digital Library
Stress relief techniques for reducing thermal fatigue in solder joints
The most effective method for relieving stress on foam encapsulated solder joints caused by thermal cycling is using silicone sleeving over component lead wires. The use of 128 kg/m/sup 3/ (8 lbs/ft/sup 3/) polyurethane foam rather than 320 kg/m/sup 3/ (20 lbs/ft/sup 3/) foam was advantageous only when the component leads were not sleeved. Special lead configurations were no better than a standard 90 degree bend. None of the other methods used or devices tested was better than silicone sleeving.
Date:
February 1, 1978
Creator:
Jarboe, D.M.
Object Type:
Report
System:
The UNT Digital Library
Safety analysis of the main vault at TA-41, LASL
Safety considerations discussed in this report show that special nuclear materials stored at a Los Alamos Scientific Laboratory facility (TA-41) present no inappropriate risk to workers or the public. The report addresses nuclear criticality, fire, and radioactive contamination potentials, as well as physical protection and material safeguards.
Date:
February 1, 1978
Creator:
Ehrenkranz, T. E.; Dahl, D. A.; Plassmann, E. H.; Pogna, R. & Smith, D. R.
Object Type:
Report
System:
The UNT Digital Library
PWR blowdown heat transfer separate-effects program: thermal-hydraulic test facility experimental data report for test 104
Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 104, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in the PWR system. Test 104 was conducted to obtain CHF in bundle 1 under blowdown conditions. The primary purpose of this report is to make the reduced instrument responses during test 104 available.
Date:
February 14, 1978
Creator:
Leon, D. M.; White, M. D.; Moore, P. A. & Hedrick, R. A.
Object Type:
Report
System:
The UNT Digital Library
PWR Blowdown Heat Transfer Separated-Effects Program. Thermal-Hydraulic Test Facility experimental data report for test 102. [PWR]
Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 102, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 102 was conducted to investigate the thermal-hydraulic response of bundle 1 under full-power steady-state and blowdown conditions.
Date:
February 1, 1978
Creator:
Clemons, V. D.; White, M. D.; Moore, P. A. & Hedrick, R. A.
Object Type:
Report
System:
The UNT Digital Library
El Dorado Micellar-Polymer Demonstration Project third annual report, June 1976--August 1977
The primary objectives of this project are to determine the economic feasibility of improved oil recovery using two micellar-polymer processes and to determine the associated benefits and problems of each process. The El Dorado Demonstration Project is designed to allow a side-by-side comparison of two distinct micellar-polymer processes in the same field so that the reservoir conditions for the two floods are as nearly alike as possible. Selection of sulfonates and polymers for both patterns was completed. Salinity changes in produced fluids and in observation well samples have shown that breakthrough of preflush (or preflood) has occurred at some wells in both patterns. Observation well sampling and logging data showed that preflush arrived earlier at the observation wells in the north pattern than the south pattern. Injectivities of the micellar system designed for the south pattern and components of that system were tested in three monitoring wells. Similarly, extensive injectivity testing of the surfactant and polymer slugs designed for the north pattern was conducted using two monitoring wells. Recommended preflush volumes for the south pattern were revised to reflect corrections in reservoir data (primarily due to the lack of the upper zone at well MP-213). Reservoir pressure forecasts of the …
Date:
February 1, 1978
Creator:
Rosenwald, G. W.; Miller, R. J. & Vairogs, J. (eds.)
Object Type:
Report
System:
The UNT Digital Library
Special purpose materials for the fusion reactor environment: a technical assessment
This technology assessment considers the following areas: (1) breeding materials, (2) coolants, (3) tritium barriers, (4) graphite and silicon carbide, (5) ceramics, (6) heat-sink materials, and (7) magnet materials. Some questions and analyses forming the assessment are described. (MOW)
Date:
February 1, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Diffusion welding multifilament superconductive composites
Diffusion welding is shown to be a feasible method for joining composites of niobium-titanium superconductor alloy filaments in a pure copper matrix. Good results were repeatedly obtained using 15/sup 0/ scarf joints welded with externally heated tooling and simple uniaxial compression loading in a conventional hydraulic press. Weld cycles of less than one hour total elapsed time were readily attainable. Through proper closed-die design, it was possible to increase welding pressure sufficiently to use relatively low temperatures to coincide with the optimum aging heat treatment of the superconductor alloy. This temperature limitation is important to retain optimal superconductor properties. Confirming measurements of critical current density of welded joints at 4.2/sup 0/K are in progress. In the welded joints made under optimum conditions, there is bonding of all constituents, including superconductor filaments. Weld tooling which effectively contains the relatively fluid matrix, and resists deformation during repeated weld cycles, is essential to the successful application of the diffusion welding process to these composites.
Date:
February 27, 1978
Creator:
Witherell, C.E.
Object Type:
Article
System:
The UNT Digital Library
Spatial distribution measurements of fission neutrons in water as an oxygen data test
The spatial distribution of the total neutron density from a /sup 252/Cf source in pure water was measured to high statistical precision at distances from 11 to 80 cm from the source. Assuming the adequacy of the ENDF/B-IV hydrogen, and reasonable constraints on the fission spectrum mean energy, good agreement between experiment and a one-dimensional transport calculation was obtained for both ENDF/B-III and IV oxygen, with Version III slightly better. However, small residual differences remained that could not be removed by adjustment of the spectrum mean energy alone.
Date:
February 1978
Creator:
Green, L. & Ullo, J.J.
Object Type:
Report
System:
The UNT Digital Library
Experiment data report for Semiscale Mod-1 Tests S-28-7, S-28-9, and S-28-12. [PWR]
Recorded test data are presented for Tests S-28-7, S-28-9, and S-28-12 of the Semiscale Mod-1 steam generator tube rupture test series. These tests are among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Tests S-28-7, S-28-9, and S-28-12 were conducted from initial conditions of 15 736 kPa and 557 K, 15 754 kPa and 556 K, and 15 704 kPa and 559 K, respectively, to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood transient following a simulated double-ended offset shear of the broken loop cold leg piping. The specific objective of these tests was to refine the definition of the upper limit of steam generator tube ruptures at which high peak cladding temperatures occur, as set by Test S-28-1. During these tests, cooling water was injected into the cold leg of the intact and broken loops to simulate emergency core coolant in a PWR. Thirty (Test S-28-7), 34 (Test S-28-9), and 20 (Test S-28-12) steam generator tube ruptures were simulated by a controlled injection from a heated accmulator into the intact loop hot leg.
Date:
February 1, 1978
Creator:
Esparza, V.; Collins, B.L.; Sackett, K.E. & Coppin, C.E.
Object Type:
Report
System:
The UNT Digital Library
LOFT emergency core coolant thermal analysis Class I review
The LOFT Emergency Core Coolant Piping Thermal Analysis was checked to insure that the calculations made would conservatively satisfy the requirements in the LOFT technical specifications. Some of the boundary conditions used have not been shown to be conservative and require review and possible re-analysis. One of the thermal models used could not be clearly related to a specific part of the piping geometry and requires further explanation. The remainder of the models, the use of the SIMIR code and the other boundary conditions appear conservative and reflect normal thermal analysis methodology and practice. However, the use of constant, rather than temperature varying, thermal properties for some materials may introduce a slight error in these analyses.
Date:
February 3, 1978
Creator:
Kinnaman, T.L.
Object Type:
Report
System:
The UNT Digital Library
DYMAC demonstration program: Phase I experience
The DYnamic MAterials Control (DYMAC) project tested a prototype system at the DP Site LASL plutonium facility, which consisted of a computerized accounting system based on material balancing by unit process. Transactions were written to describe the movement of material from one unit process to another. In the DYMAC prototype a specially designed computer program handled transactions that operators entered into the system via a terminal in the processing area. The transactions contained the same information that is used in the present LASL paper accounting system to create an inventory. During a 6-week period the DYMAC system operated in parallel with the paper system. At the end of the period results showed the DYMAC system was able to keep an accurate and timely inventory. Concurrent with testing the transaction-handling program, the project operated several nondestructive assay instruments in a glovebox environment, specifically the electronic balance, solution assay instrument, and thermal-neutron coincidence counter. From the instrument operation logs, project personnel were able to identify operational problems and incorporate design changes in the instrumentation for the new facility.
Date:
February 1, 1978
Creator:
Augustson, R.H.
Object Type:
Report
System:
The UNT Digital Library
Steam generator tube denting simulation testing. [PWR]
Tube denting has been reported in steam generators in a number of commercial nuclear power plants in recent years. In order to aid in understanding of the mechanism leading to tube denting in the steam generators, a Bettis laboratory test program was initiated to attempt to reproduce tube denting and to investigate the effects of chemistry, design, and temperature. The results of the tests indicate that denting can be reproduced in the small model steam generator test apparatus devised for this testing. Denting was observed under carbon steel support plates in seawater-contaminated secondary water in a test with hydrazine-ammonia chemistry and a primary water inlet temperature of 590/sup 0/F and in a test with hydrazine-morpholine chemistry and a primary water inlet temperature of 545/sup 0/F. The parameters of these two tests simulate conditions in a typical commercial steam generator and the Shippingport Atomic Power Station steam generators, respectively.
Date:
February 1978
Creator:
Battaglia, P. J. & Singley, W. J.
Object Type:
Report
System:
The UNT Digital Library
Neutron detector suitcase for the Nuclear Emergency Search Team
A portable high-efficiency neutron detection system has been constructed for the Nuclear Emergency Search Team. It includes an alarm system based on time interval measurements of the incoming neutron detection pulses. The system is designed for transportation by vehicle in searching for neutron-emitting radioactive materials.
Date:
February 1, 1978
Creator:
Dowdy, E.J.; Henry, C.N.; Hastings, R.D. & France, S.W.
Object Type:
Report
System:
The UNT Digital Library
Geothermal energy prospects for the next 50 years
Three facets of geothermal energy--resource base, electric power potential, and potential nonelectric uses--are considered, using information derived from three sources: (1) analytic computations based on gross geologic and geophysical features of the earth's crust, (2) the literature, and (3) a worldwide questionnaire. Discussion is presented under the following section headings: geothermal resources; electric energy conversion; nonelectric uses; recent international developments; environmental considerations, and bibliography. (JGB)
Date:
February 1, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library