Partner
UNT Libraries Government Documents Department
5,033
Texas Historical Commission
1,248
Oklahoma Historical Society
331
UNT Libraries Special Collections
225
Chambers County Library System
12
Sachse Public Library
12
Rice University Woodson Research Center
11
Sterling Municipal Library
11
Deaf Smith County Library
8
Hopkins County Genealogical Society
6
78 More
Collection
Office of Scientific & Technical Information Technical Reports
5,002
THC National Register Collection
1,248
Oklahoma Publishing Company Photography Collection
242
Texas Digital Newspaper Program
199
KXAS-NBC 5 News Collection
195
Oklahoma Digital Newspaper Program
96
Tocker Foundation Grant
83
The Oklahoma City Times
16
University Photography Collection
16
Chickasha Newspaper Collection
13
125 More
Degree Department
Country
States
Year
Month
Day
Total field aeromagnetic map of the Long Valley Geothermal Resource Area, California by the US Geological Survey
None
Date:
January 1, 1981
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Total field aeromagnetic map of the Raft River known Geothermal Resource Area, Idaho by the US Geological Survey
None
Date:
January 1, 1981
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Total field aeromagnetic map of the Steamboat Hills known Geothermal Resource Area, Nevada
None
Date:
January 1, 1981
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Total field aeromagnetic map, Surprise Valley known Geothermal Resource Area, California by the US Geological Survey
None
Date:
January 1, 1981
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Toxicity, Bioaccumulation and Depuration of Bromoform in Five Marine Species
Bromoform has been identified as the single most abundant halogenated organic compound produced by the chlorination of marine waters. To determine the potential biological effects of its release into marine waters, short-term toxicity bioassays and 28-day uptake/28-day depuration studies were conducted with five marine species: Protothaca staminea, Mercenaria mercenaria, Crassostrea virginica, Penaeus aztecus, and Brevoortia tyrannus. The bioassay studies indicate that 96-hr LC50s ranged from approximately 7 ppm for B. tyrannus to greater than 40 ppm for P. staminea. Behavioral changes were noted in P. aztecus and B. tyrannus exposed to sublethal concentrations of bromoform. In all species tested, the uptake and depuration of bromoform was rapid. Bromoform was present in all exposed animal tissues within 24 hours and was depurated within 48 hours. In the mollusk species, there was bioaccumulation above water concentrations in the first week of exposure, and then the tissue concentrations fell to levels approximately equal to the water concentrations. The shrimp and menhaden also bioaccumulated bromoform above water concentrations in the first week of exposure, but then the tissue concentrations fell to approximately 0.4 {micro}g/g and remained at this level independent of water concentrations.
Date:
January 1, 1981
Creator:
Gibson, C. I.; Tone, F. C.; Wilkinson, P.; Blaylock, J. W. & Schirmer, R. E.
Object Type:
Report
System:
The UNT Digital Library
TRAC-BD1: transient reactor analysis code for boiling-water systems
The Boiling Water Reactor (BWR) version of the Transient Reactor Analysis Code (TRAC) is being developed at the Idaho National Engineering Laboratory (INEL) to provide an advanced best-estimate predictive capability for the analysis of postulated accidents in BWRs. The TRAC-BD1 program provides the Loss of Coolant Accident (LOCA) analysis capability for BWRs and for many BWR related thermal hydraulic experimental facilities. This code features a three-dimensional treatment of the BWR pressure vessel; a detailed model of a BWR fuel bundle including multirod, multibundle, radiation heat transfer, leakage path modeling capability, flow-regime-dependent constitutive equation treatment, reflood tracking capability for both falling films and bottom flood quench fronts, and consistent treatment of the entire accident sequence. The BWR component models in TRAC-BD1 are described and comparisons with data presented. Application of the code to a BWR6 LOCA is also presented.
Date:
January 1, 1981
Creator:
Spore, J. W.; Weaver, W. L.; Shumway, R. W.; Giles, M. M.; Phillips, R. E.; Mohr, C. M. et al.
Object Type:
Article
System:
The UNT Digital Library
TRAC calculations of a loss-of-coolant accident in a reactor scale model. [PWR]
The TRAC (Transient Reactor Analysis Code) is being developed at the Los Alamos National Laboratory as an advanced best-estimate computer program for analysis of postulated hypothetical accidents in pressurized water reactors. As a part of the TRAC developmental verification efforts, a TRAC posttest analysis of Semiscale Mod-3 Test S-07-6 was conducted. The results of this analysis show that the agreement between TRAC calculations and experimental data is not very good. In particular, TRAC does not predict the long term doncomer and core liquid level oscillations during the reflood phase.
Date:
January 1, 1981
Creator:
Pyun, J. J.
Object Type:
Article
System:
The UNT Digital Library
TRAC development and assessment status
TRAC is being developed at the Los Alamos National Laboratory to provide an advanced systems code for light-water reactor accident analysis. The released TRAC versions (P1, P1A, and PD2) were intended primarily as benchmark codes for large-break loss-of-coolant accidents but PD2 has been applied successfully to TMI-type transients and other small-break transients. A fast-running version, PFl, is currently under development to address more efficiently and accurately these types of transients. All of the released versions have been subjected to testing against separate-effects, system-effects, and integral experiments covering a wide range of scales. Assessment results indicate that PD2 does a credible job overall; needed improvements are being addressed in PFl and in modifications to PD2.
Date:
January 1, 1981
Creator:
Vigil, J. C. & Knight, T. D.
Object Type:
Article
System:
The UNT Digital Library
TRAC methods and models. [PWR]
The numerical methods and physical models used in the Transient Reactor Analysis Code (TRAC) versions PD2 and PF1 are discussed. Particular emphasis is placed on TRAC-PF1, the version specifically designed to analyze small-break loss-of-coolant accidents (LOCAs).
Date:
January 1, 1981
Creator:
Mahaffy, J.H.; Liles, D.R. & Bott, T.F.
Object Type:
Article
System:
The UNT Digital Library
TRAC-P1A independent assessment, 1979
This report presents the results of the TRAC-P1A independent assessment analyses performed during calendar year 1979. These calculations were performed with the publicly released version of the code and include separate-effects tests for vessel level swell and large-scale critical flow, integral-effects tests for the blowdown/refill/reflood phases of the large-break LOCAs, and integral-effects tests for small-break LOCAs. Although the independent assessment analyses do not represent an exhaustive study of the full range of available facilities and tests, they do represent a rigorous test of the capabilities of the code. The results indicate that the code is directly applicable to LOCA analyses; several areas have been identified for improvement in future code development. 25 refs., 79 figs.
Date:
January 1, 1981
Creator:
Knight, T.D. (comp.)
Object Type:
Report
System:
The UNT Digital Library
TRAC-PD2 analysis of FLECHT experiments. [PWR]
This report describes TRAC-PD2 calculations of FLECHT (Full Length Emergency Cooling Heat Transfer) tests 4831 and 17201. The calculations were performed as part of the TRAC-PD2 developmental assessment where the objective was to assess TRAC-PD2 reflood modeling under forced flooding conditions. Calculated and experimental values for peak fuel-rod clad temperature, clad quenching time, and rod bundle effluent rates are compared; and calculations with an approximate radiation heat-transfer model added to the basic TRAC-PD2 code are performed. Findings demonstrate the potential importance of surface-to-surface radiation heat transfer in these tests.
Date:
January 1, 1981
Creator:
Bott, T. F. & Mandell, D. A.
Object Type:
Article
System:
The UNT Digital Library
TRAC-PD2 modeling of LOFT and PWR small cold-leg breaks
The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos National Laboratory to provide advanced best-estimate predictions of postulated accidents in light-water reactors. TRAC-PD2, the latest publicly released version of the code, is currently being tested against small-break and other transients in experimental facilities; it is also being used to analyze postulated accidents in commercial power reactors. Calculated results for LOFT small-break experiments are compared to data, and the results from two small-break calculations for two different reactor systems are presented. It is concluded that TRAC-PD2 is useful for the analysis of cold-leg small-break accidents.
Date:
January 1, 1981
Creator:
Knight, T. D.; Willcutt, G. J. E. Jr. & Lime, J. F.
Object Type:
Article
System:
The UNT Digital Library
Tradeoffs in the design of multivarable feedback systems
Some of the tradeoffs involved in the design of multivariable feedback systems are examined. The problem of obtaining good loop properties at both the plant input and output and the impact of nonminimum phase zeros is addressed.
Date:
January 1, 1981
Creator:
Wall, J. E., Jr.; Doyle, J. C. & Harvey, C. A.
Object Type:
Report
System:
The UNT Digital Library
Training and technology statistical report, October 1979-September 1980
A total of 839 trainees were enrolled at TAT during the 1979 to 1980 training year. Section One of this statistical report includes information on only those 613 trainees who exited training between October 1, 1979, and September 30, 1980. Demographic, educational, and employment data on the 613 exiting trainees - graduates and nongraduates - are summarized. There were 478 graduates (78% of concluding trainees), of whom 459 were available for placement. Profile summaries of graduates and nongraduates are tabulated. Of the 459 available for placement, 432 were placed in jobs with beginning wages averaging $6.34 per hour. The estimated annual income for those who were placed, assuming 2080 h/y, was $13,187. The majority of graduates, 85.8%, were unemployed at the time they entered TAT. The remainder, 14.2% of graduates, reported wages averaging $3.62 per hour at entry to training. Projected on an annual basis, those graduates employed at entry earned $7529. Compared to the average starting wage of placed TAT trainees on their first jobs after graduation, $13,187, their increased earnings were $5658 or a 75% increase after training. During the training year there were 135 trainees who did not graduate. Exit information on these nongraduates is presented. In …
Date:
January 1, 1981
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Trajectory analysis of wet and dry deposited pollens from distant sources
The purposes of this study are to determine if an available trajectory model calculates reasonable pathways from probable source regions to the sampling site and to determine the pathways and travel times involved in selected cases of long distance pollen transport. (PSB)
Date:
January 1, 1981
Creator:
Raynor, G S; Hayes, J V & Lewis, D M
Object Type:
Article
System:
The UNT Digital Library
Transient response of a thermal buffer: a study for ISABELLE
Operation of the superconducting magnets in ISABELLE may necessitate rapid cooldown and warmup from ambient (300K) to liquid helium temperature (3K) to meet the requirements of the experimental program. Similarly, unprogrammed temperature excursions can also occur due to operator error or equipment malfunction. The coal bore tube of the magnets has a small mass relative to the more massive iron laminations and the stainless steel support tube. In addition the magnet coil, in thermal contact with the cold bore tube, has excellent heat transfer to the helium flowing through it compared to the iron mass. These two factors, mass and heat transfer, dictate that the cold bore tube will follow the temperature of the coolant more closely than the iron and hence substantial temperature gradients can exist. If the temperature difference between the coolant and the iron in the magnet exceeds 44K stress failure may occur to either the cold bore tube or the magnet dewar end cap. To preclude such failures from occuring at least two options are available. One method is to modify the magnet design by introducing flexibility between the bore tube and the end plate. Another is to introduce an insensitive thermal mass or buffer as …
Date:
January 1, 1981
Creator:
Schneider, W. J.
Object Type:
Article
System:
The UNT Digital Library
Transition-Phase Calculation of a Large, Heterogeneous-Core LMFBR
A mechanistic calculation of a complete transition-phase sequence for a large heterogeneous core LMFBR has been performed using SIMMER-II. Recriticalities occurred as the disruption progressed through a series of different subphases. The number and severity of recriticalities was directly related to the timing and scale of fuel removal and coherence of material motion. The energetics associated with transition-phase are not yet resolved but the understanding of the characteristics of disruption and the effects of uncertainties has been extended significantly.
Date:
January 1, 1981
Creator:
Luck, L. B.; Bell, C. R.; Asprey, M. W. & DeVault, G. P.
Object Type:
Article
System:
The UNT Digital Library
Transverse phase space time dependence of LAMPF's high intensity H+ beam
The LAMPF H+ injector is pulsed 120 times a second with pulse lengths from 500 to 750 ..mu..sec long. Large transients in transverse phase space, lasting 100 to 200 ..mu..sec after turn-on, are regularly observed. The magnitude of these transients appears to increase with increasing currents and source brightness. Because high-current accelerators require great precision in phase-space tailoring to avoid excessive emittance growth during acceleration, these transients cause severe operational problems and can no longer be neglected in the beam tuning procedure. Measurements of transverse phase space as a function of time for the 750 keV, 30-mA peak current H+ beam are presented.
Date:
January 1, 1981
Creator:
Hurd, J. & Browman, A.
Object Type:
Article
System:
The UNT Digital Library
Trapping and surface permeation of deuterium in Fe, Ni, and stainless steel: an ion-beam study
Ion implantation and ion beam analysis were used to investigate trapping and surface permeability for deuterium (D) in Fe, Ni, and 304 stainless steel. In He-implanted Fe containing approx. 1 nm He bubbles, D was trapped with an enthalpy of 0.75 + - 0.07 eV, referenced to a solution site. The proposed trapping mechanism is chemisorption on the walls of the bubbles. Deuterium was also bound to implantation defects, hypothesized to be vacancies and vacancy clusters, with enthalpies of 0.5 and 0.7 eV respectively. The permeability of the electropolished and air-exposed Fe surface was characterized by a recombination coefficient of K/sub L/ = 10/sup -14/ /sup + -/ /sup 0/ /sup 7/ mm/sup 4//s at a temperature of 500 K. Trapping of D was also observed in Ni and 304 stainless steel implanted with He, the measured binding enthalpy being about 0.5 eV in both cases. Bubble traps similar to those observed in Fe are presumed responsible. No surface-barrier effect was detected for Ni, implying K/sub L/ greater than or equal to 10/sup -15/ mm/sup 4//s at approx. 350 K. In contrast, for electropolished and air-exposed stainless steel, K/sub L/ less than or equal to 10/sup -19/ mm/sup 4//s at …
Date:
January 1, 1981
Creator:
Myers, S. M.
Object Type:
Article
System:
The UNT Digital Library
TREAT experimental data base regarding fuel dispersals in LMFBR loss-of-flow accidents
The reactivity feedback from fuel relocation is a central issue in the analysis of loss-of-flow (LOF) accidents in LMFBRs. Fuel relocation has been studied in a number of LOF simulations in the TREAT reactor. In this paper the results of these tests are analyzed, using, as the principal figure of merit, the changes in equivalent fuel worth associated with the fuel motion. The equivalent fuel worth was calculated from the measured axial fuel distributions by weighting the data with a typical LMFBR fuel-worth function. At nominal power, the initial fuel relocation resulted in increases in equivalent fuel worth. Above nominal power the fuel motion was dispersive, but the dispersive driving forces could not unequivocally be identified from the experimental data.
Date:
January 1, 1981
Creator:
Simms, R.; Fink, C.L.; Stanford, G.S. & Regis, J.P.
Object Type:
Article
System:
The UNT Digital Library
TREAT neutron-radiography facility
The TREAT reactor was built as a transient irradiation test reactor. By taking advantage of built-in system features, it was possible to add a neutron-radiography facility. This facility has been used over the years to radiograph a wide variety and large number of preirradiated fuel pins in many different configurations. Eight different specimen handling casks weighing up to 54.4 t (60 T) can be accommodated. Thermal, epithermal, and track-etch radiographs have been taken. Neutron-radiography service can be provided for specimens from other reactor facilities, and the capacity for storing preirradiated specimens also exists.
Date:
January 1, 1981
Creator:
Harrison, Lawrence J.
Object Type:
Article
System:
The UNT Digital Library
Treatment of coal-conversion wastewater with the powdered activated carbon-contact stabilization activated-sludge process. First semiannual technical progress report, August 1, 1980-January 31, 1981
The treatment of coal conversion wastewaters has traditionally been accomplished through the use of the activated sludge process and its various modifications. General observations have been that phenol was degraded efficiently; however, very poor removal efficiencies of thiocyanate, cyanide, and ammonia were obtained. The addition of powdered activated carbon (PAC) to the activated sludge process has been reported to result in a number of distinct advantages. Generally, however, improving the effluent water quality beyond the capabilities of conventional biological treatment and enhancing the treatability of wastewaters that inhibit or toxify biological treatment systems are the primary objectives of utilizing PAC in secondary biological treatment. The focus of the present research project is to assess the effectiveness of the powdered activated carbon-contact stabilization activated sludge process in the treatment of a coking wastewater. The purpose of the contact tank in such a process will be to provide sufficient time for the adsorbable constituents of the coking wastewater to adsorb onto the PAC. The liquor leaving the contact tank is then clarified with the concentratrated underflow receiving treatment in the stabilization tank. After stabilization the sludge is returned to the contact tank. The clarifier supernatant is then nitrified in an activated sludge-type …
Date:
January 1, 1981
Creator:
Suidan, M.T.; Pirbazari, M.; Gee, C.S. & Deady, M.A.
Object Type:
Report
System:
The UNT Digital Library
Trends in nuclear spectroscopy with (more or less) direct reactions
Recent experiments on the Gamow-Teller giant resonance are discussed with special regard to the strength sum rules. Some ideas for further investigations of pairing collective modes are presented. The emphasis is on one fermion-two boson states and on two boson transfer reactions. Finally some new experimental results from heavy ion inelastic scattering are presented and the role of such processes in the energy ion mechanisms leading to deep inelastic collisions is discussed.
Date:
January 1, 1981
Creator:
Hansen, O.
Object Type:
Article
System:
The UNT Digital Library
Tritium transport around nuclear facilities
The transport and cycling of tritium around nuclear facilities is reviewed with special emphasis on studies at the Savannah River Laboratory, Aiken, South Carolina. These studies have shown that the rate of deposition from the atmosphere, the site of deposition, and the subsequent cycling are strongly influenced by the compound with which the tritium is associated. Tritiated hydrogen is largely deposited in the soil, while tritiated water is deposited in the greatest quantity in the vegetation. Tritiated hydrogen is converted in the soil to tritiated water that leaves the soil slowly, through drainage and transpiration. Tritiated water deposited directly to the vegetation leaves the vegetation more rapidly after exposure. Only a small part of the tritium entering the vegetation becomes bound in organic molecules. However, it appears tht the existence of soil organic compounds with tritium concentrations greater than the equilibrium concentration in the associated water can be explained by direct metabolism of tritiated hydrogen in vegetation.
Date:
January 1, 1981
Creator:
Murphy, C. E. Jr. & Sweet, C. W.
Object Type:
Article
System:
The UNT Digital Library