Partner
UNT Libraries Government Documents Department
1,919
Oklahoma Historical Society
852
UNT Libraries Special Collections
554
Texas Historical Commission
81
Sterling Municipal Library
27
Deaf Smith County Library
21
UNT Libraries
14
Carl Albert Congressional Research and Studies Center
13
Burleson Public Library
11
Rice University Woodson Research Center
11
86 More
Collection
Office of Scientific & Technical Information Technical Reports
1,845
Oklahoma Publishing Company Photography Collection
629
KXAS-NBC 5 News Collection
528
Texas Digital Newspaper Program
359
Oklahoma Digital Newspaper Program
242
Tocker Foundation Grant
160
THC National Register Collection
81
The Oklahoma City Times
42
Chickasha Newspaper Collection
30
Altus Times-Democrat
28
138 More
Degree Department
Country
States
Year
Month
dc glow-discharge cleaning for accelerator
Average pressure of 1 x 10/sup -11/ torr and vacuum stability are necessary for the successful operation of the proton storage rings such as ISABELLE. Vacuum degassing at high temperature and in situ bake-out will reduce the thermoout-gassing rate of the beam tubes to approx. 10/sup -13/ Tl/cm/sup 2/ sec, therefore achieving the required static pressure. The vacuum instability caused by beam-induced ion desorption can be solved by dc glow discharge cleaning. With evidence from this study, the present understanding of glow discharge in a cylindrically symmetric geometry is reviewed. Argon and argon/oxygen mixture serve as plasmas in the glow. The role of oxygen in cleaning the beam tubes during the glow discharge is demonstrated experimentally. Glow discharge cleaning with and without bake-out is also studied.
Date:
January 1, 1982
Creator:
Chou, T. S. & Hseuh, H. C.
Object Type:
Report
System:
The UNT Digital Library
RETADDII: modeling long-range atmospheric transport of radionuclides
A versatile model is described which estimates atmospheric dispersion based on plume trajectories calculated for the mixed layer. This model allows the treatment of the dispersal from a source at an arbitrary height while taking account of plume depletion by dry and wet deposition together with the decay of material to successor species. The plume depletion, decay and growth equations are solved in an efficient manner which can accommodate up to eight pollutants (i.e. a parent and seven serial decay products). The code is particularly suitable for applications involving radioactive chain decay or for cases involving chemical species with successor decay products. Arbitrary emission rates can be specified for the members of the chain or, as is commonly the case, a sole emission rate can be specified for the first member. The code, in its current configuration, uses readily available upper-air wind data for the North American continent.
Date:
January 1, 1982
Creator:
Murphy, B. D.
Object Type:
Article
System:
The UNT Digital Library
High-sensitivity transuranic waste assay by simultaneous proton and thermal-neutron interrogation using an electron linear accelerator
Simultaneous photon and neutron interrogation from electron linear accelerator pulses is used as the basis for a unique assay technique for transuranics. Both prompt and delayed neutrons from the induced fissions are counted on a single detection system, and the contributions from each interrogating flux are resolved. Detection limits (3 sigma) for /sup 239/Pu were estimated to be 3 mg for prompt fission neutrons and 6 mg for delayed neutrons. The technique also provides a clear distinction between fissile and fertile nuclides.
Date:
January 1, 1982
Creator:
Franks, L. A.; Pigg, J. L.; Caldwell, J. T.; Cates, M. R.; Kunz, W. E. & Noel, B. W.
Object Type:
Article
System:
The UNT Digital Library
Potential application of a single-particle aerosol spectrometer for monitoring aerosol size at the DOE filter test facilities
At each of the three Department of Energy (DOE) filter test facilities (FTF), a commercial single particle aerosol spectrometer, the LAS-X, was used to demonstrate that the test aerosol produced by each of the Q107 high efficiency particulate air (HEPA) filter test systems was polydisperse with a geometric standard deviation greater than 1.35, and a geometric mean diameter less than 0.2 ..mu..m. These results confirm the work of others that the OWL (mechanical analyzer) is inadequate for assuring that these test aerosols are monodisperse with a mean diameter of 0.3 ..mu..m. Use of the LAS-X for monitoring aerosol size was evaluated. The LAS-X is relatively insensitive to changes in aerosol concentration and refractive index over the range of interest for filter testing. It appears that the LAS-X would provide a better instrument for monitoring aerosol size, and would permit the FTF test operator to adjust the test aerosol to approximate the size characteristics currently recommended for this test.
Date:
January 1, 1982
Creator:
Salzman, G.C.; Ettinger, H.J.; Tillery, M.I.; Wheat, L.D. & Grace, W.K.
Object Type:
Article
System:
The UNT Digital Library
Production of. gamma. ,. pi. /sup 0/ and eta at large transverse momenta
A measurement of direct photon production, as well as of ..pi../sup 0/ and eta meson production, has been performed at Fermilab. Data were taken for 200 GeV/c p and ..pi../sup +/ incident on Be, C and Al targets. The ratio of ..gamma../..pi../sup 0/ inclusive cross sections is presented for transverse momenta between 2 and 5 GeV/c.
Date:
January 1, 1982
Creator:
Biel, J.; Bromberg, C. & Brown, B.
Object Type:
Report
System:
The UNT Digital Library
A = 4 0/sup +/ - 1/sup +/ binding-energy difference
The A = 4 ..lambda..-hypernuclei provide a rich source of information about the s-wave properties of the fundamental hyperon-nucleon (YN) force as well as offer a unique opportunity to investigate the complications that arise in calculations of the properties of bound systems in which one baryon (here the ..lambda..) with a given isospin couples strongly to another (the ..sigma..) with a different isospin. The ..lambda../sup 4/H - ..lambda../sup 4/He isodoublet ground-state energies are not consistent with a charge symmetry hypothesis for the YN interaction. The (spin-flip) excitation energies are quite sensitive to the ..lambda..N - ..sigma..N coupling of the YN interaction. In particular, when one represents the free YN interaction in terms of one-channel effective ..lambda..N potentials, the resulting 0/sup +/ (ground) state and 1/sup +/ (excited) spin-flip state are inversely ordered in terms of binding energies, the 1/sup +/ state being more bound. It is the ..sigma.. suppression that results from the reduced strength of the ..lambda..N - ..sigma..N off-diagonal coupling potential when the trinucleon core is restricted to isospin-1/2 which we study here. We find this spin-isospin suppression of the ..lambda..-..sigma.. conversion, which is due to the composite nature of the nuclear cores of the ..lambda../sup 4/H and …
Date:
January 1, 1982
Creator:
Gibson, B. F. & Lehman, D. R.
Object Type:
Article
System:
The UNT Digital Library
Sensitivity study of neutron transport through standard and rebar concrete
An investigation is under way at ORNL to (1) develop a data base pertinent to the transport of neutrons through thick concrete shields, (2) use the data base in an energy group boundary selection and collapsing scheme, and (3) develop a simple methodology to access the data base to provide rapid solutions to practical shielding problems. This paper describes work carried out to fulfill objective (1), the work consisting of calculations of the transport of fission neutrons through 1- and 2-m-thick slabs of standard concrete and rebar (steel-reinforced) concrete, together with calculations of the sensitivities of the results to total, absorption, and elastic cross sections. The transport calculations were performed with the one-dimensional discrete ordinates code ANISN in both forward and adjoint modes. The DLC-41C/VITAMIN-C cross-section library (171 neutron, 36 gamma groups) was employed, with a P/sub 3/ cross-section expansion and an S/sub 16/ angular quadrature. In all cases the fission source was assumed to be distributed within the first 1-cm thickness of the slab and the detector was assumed to occupy the last 1-cm thickness of the slab. For the rebar concrete the slab constituents were homogenized, with the horizontal and vertical No. 11 reinforcing steel rods comprising 7.6 …
Date:
January 1, 1982
Creator:
Bhuiyan, S. I.; Roussin, R. W. & Lucius, J. L.
Object Type:
Article
System:
The UNT Digital Library
Tested method to minimize plutonium assay discrepancies between laboratories
Plutonium assay differences are frequently observed between laboratories exchanging plutonium dioxide powders. These differences are commonly the result of chemical changes and/or nonhomogeneities in sampled materials. The irregularities are often caused by moisture absorption during sampling, packaging, shipment, and storage of the materials. A method is proposed which eliminates the effects of chemical change in samples, particularly moisture absorption, and minimizes sampling error. A nondestructive thermal watts/gram test on every preweighed sampled and total dissolution of these samples for chemical assay are the primary features which make this method effective. Because this method minimizes the error related to exchange material, it is possible to design an interlaboratory exchange program which demonstrates the assay capabiliies of the participants. In an experiment performed to demonstrate the effectiveness of this method, three PuO/sub 2/ batches of varying isotopic composition were synthesized at Mound to be used in the exchange tess. Powder sample aliquots from each batch were weighed directly into their vials under controlled atmospheric conditions. Calorimetric heat measurements were made on each vial to test homogeneity and verify sample weight. Six vials of each batch were chemically assayed at Mound and six at NBL (New Brunswick Laboratory). Both laboratories chose controlled-potential coulometry …
Date:
January 29, 1982
Creator:
Seiler, R. J.; Goss, R. L.; Rodenburg, W. W. & Rogers, D. R.
Object Type:
Report
System:
The UNT Digital Library
MC3644 detonator development status report for the period ending October 30, 1981
The MC3644 detonator is being developed as a replacement for the MC3132 flying plate detonator in the parachute deployment system of the B83 weapon. The MC3644 is a CP, deflagration-to-detonation transition device. Two models are being developed: an interim design using the MC3423 ignitor and a new production version with a one-piece ignitor/header assembly. Features of both designs are described. Results of development tests involving the interim design are presented. No-fire sensitivity test and proof-test results with the WR version are also included. The development program is on schedule.
Date:
January 1, 1982
Creator:
Jacobson, A. K.
Object Type:
Report
System:
The UNT Digital Library
Novel experiments for understanding the shallow-land burial of low-level radioactive wastes
Three field experiments that will provide data on water movement in SLB facilities are described. The experiments are designed to measure water movement, to quantify techniques to control water movement and to determine the effects of surface moisture content fluctuations on liquid and vapor movement back to the surface.
Date:
January 1, 1982
Creator:
DePoorter, G. L.; Abeele, W. V.; Hakonson, T. E.; Burton, B. W. & Perkins, B. A.
Object Type:
Article
System:
The UNT Digital Library
Standards for holdup measurement
Holdup measurement, needed for material balance, depend intensively on standards and on interpretation of the calibration procedure. More than other measurements, the calibration procedure using the standard becomes part of the standard. Standards practical for field use and calibration techniques have been developed. While accuracy in holdup measurements is comparatively poor, avoidance of bias is a necessary goal.
Date:
January 1, 1982
Creator:
Zucker, M.S.
Object Type:
Article
System:
The UNT Digital Library
Controlled air incineration of hazardous chemical waste at the Los Alamos National Laboratory. [Polychlorinated biphenyl, pentachlorophenol]
An incineration system, originally demonstrated as a transuranic (TRU) waste volume-reduction process, is described. The production-scale controlled air incinerator using commercially available equipment and technology was modified for solid radioactive waste service. The same incinerator and offgas treatment system has been modified further for use in evaluating the destruction of hazardous liquid wastes such as polychlorinated biphenyls (PCBs) and hazardous solid wastes such as pentachlorophenol (PCP)-treated wood. Results of a PCP-treated wood incineration test show a PCP destruction efficiency of greater than 99.99% in the primary chamber for the operating conditions investigated. Conditions and results for this test are described.
Date:
January 1, 1982
Creator:
Stretz, L. A.; Borduin, L. C.; Draper, W. E.; Koenig, R. A. & Vavruska, J. S.
Object Type:
Article
System:
The UNT Digital Library
End effects on elbows subjected to moment loadings. [PWR; BWR]
So-called end effects for moment loadings on short-radius and long-radius butt welding elbows of various arc lengths are investigated with a view toward providing more accurate design formulas for critical piping systems. Data developed in this study, along with published information, were used to develop relatively simple design equations for elbows attached at both ends to long sections of straight pipe. These formulas are the basis for an alternate ASME Code procedure for evaluating the bending moment stresses in Class 1 nuclear piping (ASME Code Case N-319). The more complicated problems of elbows with other end conditions, e.g., flanges at one or both ends, are also considered. Comparisons of recently published experimental and theoretical studies with current industrial code design rules for these situations indicate that these rules also need to be improved.
Date:
January 1, 1982
Creator:
Rodabaugh, E. C. & Moore, S. E.
Object Type:
Article
System:
The UNT Digital Library
Experimental evaluation of the differential die-away pulsed-neutron technique for the fissile assay of hot irradiated fuel waste
Hot irradiated fuel waste packages containing self neutron sources up to 10/sup 7/ n/s may be assayed successfully with a 25-mg /sup 239/Pu detection sensitivity using a differential die-away fissile assay system based on a Sandia-designed 14-MeV neutron generator. With a minor design change, our system can accommodate contact gamma dose rates up to 10/sup 4/ R/h with no loss of fissile assay sensitivity.
Date:
January 1, 1982
Creator:
Caldwell, J.T. & Kunz, W.E.
Object Type:
Article
System:
The UNT Digital Library
Development of significantly improved catalysts for coal liquefaction and upgrading of coal extracts. Quarterly progress report No. 4, July 1-September 30, 1982
Cold flow ebullation tests to determine the ranges of operability of bead catalysts continued. Data reported show the effects of higher catalyst density, wider particle size distributions, and higher fluid viscosity on ebullation of bead catalysts. A relation for determining limiting diameters in a liquid-solid fluidized bed was developed. Correlation of the three-phase data is being investigated. The CSTR Catalyst Aging Test Unit is described. The system operates under computer control. High pressure hydrogen and coal slurry are fed continuously to a one-liter stirred autoclave. High pressure nitrogen for inerting and flush oil are used in the event of an interlock shutdown. The product is passed to a 3-gallon collection vessel or to a smaller sampling vessel during material balance periods. The gas disentrains from the mixture and is scrubbed. Analytical techniques to be used in the course of the catalyst testing program were evaluated. H-COAL PDU products and SRC-II Heavy distillate were analyzed. Standard deviations for many of the procedures were determined. Specific methods are summarized. Development of surface analytical techniques to study coal liquefaction catalysts focused on used Amocat 1A catalysts from coal run 10 at the H-COAL Pilot Plant. Preliminary results of analysis by ESCA and x-ray …
Date:
January 1, 1982
Creator:
Sinha, V. T.; Kutzenco, P. D.; Preston, W. J.; Brinen, J. S.; Graham, S. W.; Butensky, M. et al.
Object Type:
Report
System:
The UNT Digital Library
Simulated monitor display for CCTV
Two computer programs have been developed which generate a two-dimensional graphic perspective of the video output produced by a Closed Circuit Television (CCTV) camera. Both programs were primarily written to produce a graphic display simulating the field-of-view (FOV) of a perimeter assessment system as seen on a CCTV monitor. The original program was developed for use on a Tektronix 4054 desktop computer; however, the usefulness of this graphic display program led to the development of a similar program for a Hewlett-Packard 9845B desktop computer. After entry of various input parameters, such as, camera lens and orientation, the programs automatically calculate and graphically plot the locations of various items, e.g., fences, an assessment zone, running men, and intrusion detection sensors. Numerous special effects can be generated to simulate such things as roads, interior walls, or sides of buildings. Other objects can be digitized and entered into permanent memory similar to the running men. With this type of simulated monitor perspective, proposed camera locations with respect to fences and a particular assessment zone can be rapidly evaluated without the costly time delays and expenditures associated with field evaluation.
Date:
January 1, 1982
Creator:
Steele, B. J.
Object Type:
Article
System:
The UNT Digital Library
Space nuclear safety and fuels program. Progress report
This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems. These studies are conducted by Los Alamos National Laboratory for the Office of Coordination and Special Projects of the US Department of Energy. Because most of the studies discussed here are ongoing, results and conclusions may change as the work continues. Published reference of the results cited in this report should not be made without explicit permission from the person in charge of the work.
Date:
January 1, 1982
Creator:
Bronisz, S. E.
Object Type:
Report
System:
The UNT Digital Library
Simple small-polaron model for the hydrogen-concentration dependence of hydrogen diffusion in Nb
We have generalized simplified small polaron models for the tunneling of interstitials in solids to include interactions between the diffusing particles. This is applied to the calculation of the average hopping rate of hydrogen in Niobium as a function of hydrogen concentration for small concentrations, i.e. for an H/Nb ratio (c) of .06 or less. The hopping of a single H under the influence of nearby, stationary H's was treated. The interactions between interstitials include a hard-core repulsion and a lattice-mediated strain interaction. The tunneling transfer integral was taken to depend on the displacements of nearby Nb atoms. Only tunneling via the ground vibrational level of the interstitials was tested. For c less than or equal to .06, the calculated increase in the hopping activation energy as a function of c was linear in c and comparable in magnitude with the experimental increase. Our simplified-model results show that the strain interaction between H's in Nb is important for their diffusion and that this interaction needs to be included in whatever more elaborate diffusion models are developed.
Date:
January 1, 1982
Creator:
Tonks, D.L. & Silver, R.N.
Object Type:
Article
System:
The UNT Digital Library
Releases of radioactivity at the Savannah River Plant, 1954-1980
This report contains summaries of releases of radioactivity to onsite seepage basins and to plant effluents for each year since plant startup (1954 through 1980). Releases for the years 1954 through 1959 were reassessed in 1974 and assigned release values for specific long-lived radionuclides. These long-lived radionuclides (half-lives greater than 1 year) are the only radionuclides included for the years 1954 through 1970. Since 1970 all detectable radionuclides have been included. Measured migration o radionuclides from F-, H-, and K-Area seepage basins and desorption of /sup 137/Cs from the Four Mile Creek stream bed are included in Summary B of this report. Summaries of monthly releases for 1979 and 1980 and total SRP releases by radionuclide in three categories: liquid to seepage basins, liquid to streams, and atmospheric are also included. Monthly releases for 1979 are included because the 1979 issue of this report was not published. All 1979 data are included in this report.
Date:
January 1, 1982
Creator:
Ashley, C.; Zeigler, C. C. & Culp, P. A.
Object Type:
Report
System:
The UNT Digital Library
Operating experience with a liquid-hydrogen fueled Buick and refueling system
An investigation of liquid-hydrogen storage and refueling systems for vehicular applications was made in a recently completed project. The vehicle used in the project was a 1979 Buick Century sedan with a 3.8-L displacement turbocharged V6 engine and an automatic transmission. The vehicle had a fuel economy for driving in the high altitude Los Alamos area that was equivalent to 2.4 km/L of liquid hydrogen or 8.9 km/L of gasoline on an equivalent energy basis. About 22% less energy was required using hydrogen rather than gasoline to go a given distance based on the Environmental Protection Agency estimate of 7.2 km/L of gasoline for this vehicle. At the end of the project the engine had been operated for 138 h and the car driven 3633 km during the 17 months that the vehicle was operated on hydrogen . Two types of onboard liquid-hydrogen storage tanks were tested in the vehicle: the first was an aluminum Dewar with a liquid-hydrogen capacity of 110 L; the second was a Dewar with an aluminum outer vessel, two copper vapor-cooled thermal radiation shields, and a stainless steel inner vessel with a liquid-hydrogen capacity of 155 L. The Buick had an unrefueled range of about …
Date:
January 1, 1982
Creator:
Stewart, W.F.
Object Type:
Article
System:
The UNT Digital Library
Two bismuth sulfate-sulfuric acid hybrid water-splitting cycles. Proposed antimonyl sulfate cycle
Some experimental work is presented that is related to two hybrid thermochemical cycles for the production of hydrogen which involve bismuth trisulfate and/or bismuth oxysulfates. Omitting statement of the steps for decomposition of SO/sub 3/ and the electrochemical formation of H/sub 2/ and H/sub 2/SO/sub 4/ from SO/sub 2/ and H/sub 2/O, the high and low temperature reactions are: Cycle I - Bi/sub 2/(SO/sub 4/)/sub 3/ = Bi/sub 2/O/sub 2/ /sub 3/ (SO/sub 4/)/sub 0/ /sub 7/ + 2.3 SO/sub 3/; and Bi/sub 2/O/sub 2/ /sub 3/(SO/sub 4/)/sub 0/ /sub 7/ + 2.3 H/sub 2/SO/sub 4/ = Bi/sub 2/(SO/sub 4/)/sub 3/ + 2.3 H/sub 2/O. Cycle II - Bi/sub 2/O(SO/sub 4/)/sub 2/ = Bi/sub 2/O/sub 2/ /sub 3/(SO/sub 4/)/sub 0/ /sub 7/ + 1.3 SO/sub 3/; and Bi/sub 2/O/sub 2/ /sub 3/(SO/sub 4/)/sub 0/ /sub 7/ + 1.3 H/sub 2/SO/sub 4/ = Bi/sub 2/O(SO/sub 4/)/sub 2/ + 1.3 H/sub 2/O. Equilibrium sulfur trioxide pressures are given graphically for three solid-gas equilibria involving Bi/sub 2/(SO/sub 4/)/sub 3/, ..cap alpha..- and ..beta..-Bi/sub 2/O(SO/sub 4/)/sub 2/, and Bi/sub 2/O/sub 2/SO/sub 4/. An improved method of carrying out the low temperature step for Cycle I is presented which may provide a remedy to a …
Date:
January 1, 1982
Creator:
Jones, W.M.
Object Type:
Article
System:
The UNT Digital Library
D7 debris bed experiment - heat removal from a shallow, stratified UO/sub 2/-sodium particle bed. [In ACPR reactor]
The D7 debris bed experiment is one in a series of experiments being conducted to investigate the coolability of fragmented reactor mterials. The D7 experiment is the second experiment which investigates heat removal from a stratified bed. The significance of particle stratification was demonstrated by the D6 experiment, which exhibited lower dryout powers of a factor of approximately two when compared to mixed beds. In addition to investigating a shallower bed as compared to the D6 experiment, the D7 experiment investigates a wider range of sodium subcooling achievable during the experiment.
Date:
January 1, 1982
Creator:
Mitchell, G W
Object Type:
Article
System:
The UNT Digital Library
Verification of the three-dimensional thermal-hydraulic models of the TRAC accident-analysis code. [PWR]
The Transient Reactor Analysis Code (TRAC) being developed at Los Alamos National Laboratory provides a best-estimate prediction of the response of light water reactors or test facilities to postulated accident sequences. One of the features of the code is the ability to analyze the vessel and its heated core in three dimensions. The code is being used to analyze the results of tests in a large-scale reflood test facility built in Japan, known as the Cylindrical Core Test Facility (CCTF). Two test runs have been analyzed that are useful for verification of the three-dimensional analysis capability of the TRAC code. One test began with an initial temperature skew across the heated core. The second test had a large radial power skew between the central and peripheral assemblies. The good agreement between the calculation and the experiment for both of these experiments demonstrates the three-dimensional analysis capability of the TRAC code.
Date:
January 1, 1982
Creator:
Motley, F.
Object Type:
Article
System:
The UNT Digital Library
Gamow-Teller strength functions and neutrino problems
A quantitative understanding of spin strengths in nuclei is of vital importance in studies of nuclear double beta decay and in solar neutrino spectroscopy. The current status of these problems is outlined.
Date:
January 1, 1982
Creator:
Haxton, W. C.
Object Type:
Article
System:
The UNT Digital Library