Partner
Oklahoma Historical Society
10,431
UNT Libraries Special Collections
4,145
UNT Libraries Government Documents Department
2,622
Rosenberg Library
1,472
Abilene Public Library
363
Sterling Municipal Library
363
Hopkins County Genealogical Society
360
Denton Public Library
332
Hardin-Simmons University Library
331
Brownwood Public Library
311
199 More
Collection
Texas Digital Newspaper Program
8,254
Oklahoma Publishing Company Photography Collection
7,708
Tocker Foundation Grant
3,700
Oklahoma Digital Newspaper Program
2,463
KXAS-NBC 5 News Collection
2,334
University Photography Collection
1,675
Harris and Eliza Kempner
1,473
Office of Scientific & Technical Information Technical Reports
1,344
Abilene Library Consortium
1,048
Ladd & Katherine Hancher Library Foundation
1,016
336 More
Serial/Series Title
Degree Department
Degree Discipline
Degree Level
Country
States
Decade
Year
Month
SMEAR STUDY OF D205 (CHEMICAL ENGINEERING BUILDING)
The smear study shows that at least 80% of the floorsmear surveys which were made in a clear area of the Chemical Engineering Building during the course of this study indicated radioactivity equal to or less than 10 d/m/ ft/sup 2/ alpha and equal to or less than 200 d/m/ft/sup 2/ beta-gamma. The smear survey technique is excellent for use in a highhazard area, such as a Pu facility. It is capable of detecting as little as 10 d/m/ft/sup 2/ of alpha contamination with a high degree of confidence. The smear survey is also useful in determining whether the radioactivity on an item is low enough so that it may be removed from an active area. (auth)
Date:
July 1, 1962
Creator:
Marchetti, F.P.
Object Type:
Report
System:
The UNT Digital Library
Physics Division Summary Report, April-May 1962
None
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
EBWR Reactor Pressure Vessel Revisions for Instrumentation and Increased Steam Output
The procedures developed and utilized for the addition of connections to the EBWR pressure vessel after three yesrs of intermittent operation at the 20- Mw(t) design heat output are described. Major nozzle connections to the pressure vessel were made during two separated periods and under different conditions of vessel content. The details of the conversion sre discussed under the following topics: nozzle design, preparations, and nozzle installation. Diagrams and photographs are included. Radioactive particulate material transport and trapped radioactive particulate matter sre discussed. (M.C.G.)
Date:
January 1, 1962
Creator:
Kettles, T.L. & Balai, N.
Object Type:
Report
System:
The UNT Digital Library
DIFFUSION OF Zr$sup 95$ IN BODY-CENTERED CUBIC IODIDE ZIRCONIUM
Chemically purifled Zr/sup 95/ was used in determining selfdiffusion coefficients in the body-centered cubic phase of iodide zirconium over the temperature range of 900 to 1750 deg C. In order to minimize effects of build-in of the daughter isotope Nb/sup 95/, all heat treatments were completed within 48 hr after the purification. The temperature dependence of the diffusion coefflcients could not be described by the usual Arrhenius-type equation. Instead, apparent values of the frequency factor D/sub o/ and the activation energy Q varied from 4.8 x 10/sup -6/ to 2.5 x 10/sup -2/ cm/sup 2//sec and 20700 to 46900 cal/mole, respectively, between the lower and upper extremities of the temperature range. Empirical treatment of the data indicated that Q is a linear function of temperature and that D/sub o/ varies with a power of the temperature. The data may be described in terms of the alpha to BETA transition temperature of 1136 deg K and the absolute temperature of the heat treatments by the following equation: D = 3 x 10/sup -6/ (T/1136)/sup 15.6/ exp (--19600 + 31(T -1136)/RT) cm/sup 2//sec. (auth)
Date:
September 1, 1962
Creator:
Lundy, T.S. & Federer, J.I.
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
Hallam Nuclear Power Facility Preoperational Test Completion Report Dry Criticality
A dry criticality test was carried out to determine the minimum critical mass of the HNPF Core without sodium. A subcritical calibration of the central control rod was performed and the relative reactivity worths of the inner ring of six control rods were determined. The extrapolated critical loading for the various plots after each incremental fuel loading with all rods out is shown. A tabulation is presented of multiplication data taken throughout the dry critical test. In order to find the relative integral reactivity worth of the central control rod in the dry critical loading, subcrltical multiplication data were obtained. The test completion criteria as stated in the test procedure were met. (M.C.G.)
Date:
February 24, 1962
Creator:
Kempt, H. C. & Corcoran, W. P.
Object Type:
Report
System:
The UNT Digital Library
Diffusion in Ceramic Systems. A Selected Bibliography
References (165) on diffusion in ceramic systems such as oxides, silicates and glasses, borides, and carbides and graphite, are given to books, reports, and U.S. and foreign journals published from 1904 to 1961. Data on the frequency factor, Da, and activation energy, Q, are given for various elements and systems. A separate author index is also included. (P.C.H.)
Date:
May 1, 1962
Creator:
Berard, M. F.
Object Type:
Report
System:
The UNT Digital Library
EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report, October-December 1960
>The effects of an ultrasonic field on the maximum nucleate heat flux that can be sustained by boiling water in a flow system are being investigated. Design and procurement of apparatus is underway. (M.C.G.)
Date:
October 31, 1962
Creator:
Romie, F.E.
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report, January 1962
None
Date:
June 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
Primary Plant Self-Actuated Relief Valve Operation. Core I, Seed 3. Test Evaluation. Section 2
A test was conducted on August 12 to 13, l961, on the operation of the four reactor coolant loop relief valves and the four purification system relief valves. The results indicated proper operation. (D.L.C.)
Date:
January 12, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Specifications and Fabrication Procedures for Type 3 Neutron Absorber Sections
The specification contains information concerning the material, process, and product requirements to be met by the fabricator. (J.R.D.)
Date:
April 25, 1962
Creator:
Edgar, E. C. & Clayton, H. R.
Object Type:
Report
System:
The UNT Digital Library
Comparison of Gaseous Waste Handling Systems for PL-3
Gaseous waste handling systems are compared for direct and indirect boiling water and pressurized water reactors for PL-3 application. Areas that are common to the various concepts are not discussed since they do not enter into a comparison study. The major differences present are in the handling of active gases released to or held in the primary system coolant. These gases which could be present, their possibIe release from the system, and the necessary processing requirements are discussed in detail. Sufficient information is presented to enable one to analyze the methcds required to remove gaseous activity present in other size and type pressurized and boiIing water reactors. (auth)
Date:
February 28, 1962
Creator:
Noble, J. H. & Duke, E. E.
Object Type:
Report
System:
The UNT Digital Library
Effect of Solute Atoms Upon Vacancy Climb of Prismatic Dislocations in Al- 5% Mg Alloy
The climb rate of prismatic dislocations in quenched Al-5% Mg Alloy was studied by bulk annealing and also by high-temperature electron microscopy of thin foils, In bulk and thin-foil specimens, loops and helices were always observed to grow. The activation energy was determined to be 0,95 plus or minus 0.05 ev. The results can be interpreted on the basis of a binding energy between vacancies and magnesium atoms which can be x0.1 to 0.4 ev, depending on their geometrical configuration. (auth)
Date:
September 1, 1962
Creator:
Eikum, A. & Thomas, G.
Object Type:
Report
System:
The UNT Digital Library
HRT-CHEMICAL PLANT RUN 21 SUMMARY
The multiple hydroclone system removed l83 grams of corrosion product solids in l814 hours of operation during reactor run 2l. The low removal rate was attributed to plugging of multiclone feed ports that presumably occurred during the latter part of run 20. After modifications to the reactor core and removal of the multiclone unit at the end of run 21, the reactor core was backflushed with the flow direction in the core loop reversed. During this period, the single hydroclone removed 205 grams of solids in 10.5 hours of operation. (auth)
Date:
February 12, 1962
Creator:
Yarbro, O.O.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Safety Program Semiannual Progress Report for Period Ending June 30, 1962
Progress in nuclear safety research and development is reported. Topics covered include: reactivity effects of fuel displacements in a pool-type reactor, release of fission products on out-of-pile melting of reactor fuels, release of fission products on in-pile melting of reactor fuels, fission product transport evaluations, characterization and control of accident-released fission products, nuclear safety pilot plant, preparation of reactor containment hardbook, and radiochemical plant safety studies. (M.C.G.)
Date:
August 24, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
IDAHO DIVISION SUMMARY REPORT, APRIL THROUGH SEPTEMBER 1961
Research and development progress is reported on TREAT, BORAX V, ZPR- III, EBR-II, and the reactor operations personnel training program. (M.C.G.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
DISSOLUTION OF BeO-AND Al$sub 2$O$sub 3$-BASE REACTOR FUEL ELEMENTS. PART I
Aqueous methods for recovering uranium from BeO- and Al/sub 2/O/sub 3/- base gas-cooled-reactor fuel elements are being evaluated. Two methods for processing Hastelloy-X--clad pelletized BeO-base fuels containing 60 to 70% UO/ sub 2/, such as the GCRE and MGCR, seem feasible. One method involves mechanical stripping or chopping of the cladding followed by leaching of the uranium from the fuel pellets with boiling 6-l3M HNO/sub 3/. In the other method the cladding and UO/sub 2/ are dissolved in boiling 2M HNO/sub 3/-4M HCl. In either case, most of the BeO matrix remains as an undissolved residue. Pellets containing 70% UO/sub 3/ dissolved completely in less than 20 hr in boiling 8M HNO/sub 3/ containing either 2M H/sub 2/SO/sub 4/ or 0.5M HF, producing solutions containing 4 g of uranium per liter. Fuels of high BeO content, e.g. BeO--5% UO/sub 2/, dissolved only slowly in boiling aqueous reagents. Highest initial rates were in sulfuric acid solutions, log (Rate, mg min/sup -1/cm/sup -2/) = 0.223 (H/sub 2/SO/ sub 4, M) - 2.8l and in HF--NH/sub 4/F solutions. ln boiling 5-8M NH/sub 4/F the initial dissolution rate increased from 0.07 to 3.5 mg min/sup -1/cm/sup -2/ as the HF concentration increased from 0 …
Date:
February 14, 1962
Creator:
Warren, K S; Ferris, L M & Kibbey, A H
Object Type:
Report
System:
The UNT Digital Library
ARGONNE NATIONAL LABORATORY PUBLICATIONS, JULY 1, 1961-JUNE 308 1962
A publications list, incorporating a subject index was compiled by machine methods. The publications covered are those originating at Argonne but published elsewhere. The list is arranged alphabetically by author's names and covers the period from July 1, 1961 through June 30, 1962. The subject index is a key word in context index using the title. (M.C.G.)
Date:
October 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
X-Ray Diffraction Study of Cs$sub 3$ZrF$sub 7$
None
Date:
August 1, 1962
Creator:
Robbins, G. D. & Burns, J. H.
Object Type:
Report
System:
The UNT Digital Library
Fire and Explosion Tests of Plutonium Gloveboxes
To test the fire and explosion resistance of new plutonium metallurgy gloveboxes and to obtain information pertinent to fire control, fire and explosion tests were conducted in one of the gloveboxes. It was found that over l0% oxygen is required for non-metal, and that over 5% oxygen is required for freely burning metal fires. However, metal chips will burn with as little as 1% oxygen if additional heat is furnished. Standard dry chemical, Met-L-X, and carbon dioxide extinguishers were excellent for nonmetal fires. An eutectic salt mixture was excellent for metal fires. (auth)
Date:
July 1, 1962
Creator:
Rhude, H.V.
Object Type:
Report
System:
The UNT Digital Library
Mathematical Analysis of Rippling of Type 1 Fuel Plates. Part 1
Rippling phenomena due to heating in fuel plates of SM and PM type reactors are investigated analytically using small deflection theory of plates. Temperature variations across the width of the plate are accounted for. Detailed calculations are conducted for simply supported plates. It is found that within the limitations imposed by small deflection theory that the amplitude of the plate ripples induced by the heating is directly proportional to the initial amplitude. (auth)
Date:
July 1, 1962
Creator:
Beck, S. D. & Miller, J. V.
Object Type:
Report
System:
The UNT Digital Library
Hyperfine Structure of the Electronic Ground States of Rb$sup 85$ And Rb$sup 8$$sup 7$
None
Date:
July 15, 1962
Creator:
Penselin, S.; Moran, T.; Cohen, V.W. & Winkler, G.
Object Type:
Article
System:
The UNT Digital Library
RADIOISOTOPE FUELED AUXILIARY POWER UNIT. Quarterly Progress Report No. 1, January 2-April 2, 1957
Progress on an isotope-fueled auxiliary power unit is reported. Based on the power requirements of 260 W, it was concluded that Ce/sup 144/ should be used as fuel. Estimates were made of fuel availability and unit cost and weight at power levels of 133, 300, 500, and 1000 W(e). Fuel development, boiler development, system and operational considerations, and the power conservation system are discussed. (M.C.G.)
Date:
October 31, 1962
Creator:
Silverstein, C.C. & Behmer, R.E. comps.
Object Type:
Report
System:
The UNT Digital Library
Summary of HRT Run 25
Run 25 was the final period of power operational of the HRT. The reactor was operated for periods of 62, 8, 52, and 80 hours at 5 Mw with no outward indication of fuel and core and blanket average temperatures of 270 and 230 deg C, respectively. The uranium concentration in the was 1.7 to 2.0 g U/kg D/sub 2/O. Longer periods of operation were prevented by mechanical difficulties, notably with the fuel feed pump. While the reactor was subcritical after the last of the above runs, the upper patch in the core tank wall became dislodged, allowing greater core-to-blanket mixing. The resultant blanket uranium concentration was 2.9 g U/kg D/sub 2/O. The reactor was subsequently operated at April 28, 1961. The experiment was operated at high temperature for a total of 10,866 hours. The system was critical for a total of 8,841 hours and produced 16,295 Mwhours of power. The fuel, heavy water, and some corrosion specimens were recovered, and the reactor was stored in an assembled state. (auth)
Date:
July 25, 1962
Creator:
Engel, J. R.; Bauman, H. F.; Buchanan, J. R.; Haubenreich, P. N.; Piper, H. B. & Richardson, D. M.
Object Type:
Report
System:
The UNT Digital Library