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DEVELOPMENT OF ULTRASONIC TECHNIQUES FOR THE REMOTE MEASUREMENT OF THE HRT CORE VESSEL WALL THICKNESS (open access)

DEVELOPMENT OF ULTRASONIC TECHNIQUES FOR THE REMOTE MEASUREMENT OF THE HRT CORE VESSEL WALL THICKNESS

Design and development of a remote ultrasonic inspection technique for use in measuring wall thicknesses in the HRT core vessel are described. (J.R.D.)
Date: March 15, 1962
Creator: McClung, R.W. & Cook, K.V.
Object Type: Report
System: The UNT Digital Library
DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Monthly Progress Letter for Month of February 1962 (open access)

DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Monthly Progress Letter for Month of February 1962

Major effort during the report period was directed toward the in-pile testing program. Component PuO/sub 2/ and UO/sub 2/ powder blending trials were continued along with coprecipitated powder characterization studies. Arrangements for irradiation of short exposure rabbit capsules were made. (J.R.D.)
Date: March 1, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
An Evaluation of the Uranium Contamination on the Surfaces of Alclad Uranium-Aluminum Alloy Research Reactor Fuel Plates (open access)

An Evaluation of the Uranium Contamination on the Surfaces of Alclad Uranium-Aluminum Alloy Research Reactor Fuel Plates

Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium contamination on the surfaces of the alclad uranium-- aluminum plate-tyne fuel element led to an investigation to determine the sources of uranium contamination on the fuel plate surfaces. Two possible contributors to surface contamination are external sources such as rolling-mill equipment, the most obvious, and diffusion of uranium from the uranium-aluminum alloy fuel into the aluminum cladding. This diffusion is likely because of the 600 deg C heat treatments used in the conventional fabrication process. Uranium determinations based on neutron activation analysis of machined layers from fuel plate surfaces showed that rolling-mill equipment, contaminated with highly enriched uranium, was responsible for transferring as much as 180 ppm U to plate surfaces. By careful practice where cleanliness is emphasized, surface contamination can be reduced to 0.6 ppm U/sup 235/. The residue remaining on the plate surface may be accounted for by diffusion of uranium from the fuel alloy into and through the cladding of the fuel plate. Data obtained from preliminary diffusion studies permitted a good estimate to be made of the diffusion coefficient of uranium into aluminum at 600 deg C: 2.5 x 10/sup -8/ cm//sec. To …
Date: March 19, 1962
Creator: Beaver, R. J.; Erwin, J. H. & Mateer, R. S.
Object Type: Report
System: The UNT Digital Library
Radiochemical Processing-Off-Site Transportation and Ultimate Storage Problems (open access)

Radiochemical Processing-Off-Site Transportation and Ultimate Storage Problems

Safe and economic methods of handling radioactive materials off-site are required for the successful operation of nuclear chemical plants. These occasions arise in the shipment of spent fuel, radioactive, isotopes, and liquid wastes. An unsolved problem exists in the development of techniques and sites for the final disposal of waste products. (auth)
Date: March 14, 1962
Creator: Blomeke, J. O. & Shappert, L. B.
Object Type: Report
System: The UNT Digital Library
THE SUBCRITICAL REACTOR WITH SOURCES (open access)

THE SUBCRITICAL REACTOR WITH SOURCES

The mathematical formulation of the subcritical reactor with extraneous sources is presented in detail. The solutions are presented for a two-group approximation including epithermal fission and the relationship to the usual critical reactor problem is discussed. Application of the equations to an arbitrarily complicated geometry is outlined, and an IBM-7090 program for the solution in a bare cylindrical reactor is described. (auth)
Date: March 13, 1962
Creator: Preskitt, C.A.
Object Type: Report
System: The UNT Digital Library
Stress Analysis of the SM-1A Reactor Vessel (open access)

Stress Analysis of the SM-1A Reactor Vessel

The stress analysis performed on the SM-lA reactor vessel and cover is presented. The msximum combined stress (51,360 psi in compression) occurs in the vessel cover during a 50 deg F/hr transient. A fatigue analysis of these stresses indicated that they could be applied safely at least 2500 times, and since the vessel is expected to receive less than 900 cycles, it should not suffer any fatigue damage. (auth)
Date: March 30, 1962
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A. & Aitken, C. C.
Object Type: Report
System: The UNT Digital Library
The Structures of NiZr$sub 2$, NiZr and Their Hafnium Analogs (open access)

The Structures of NiZr$sub 2$, NiZr and Their Hafnium Analogs

None
Date: March 10, 1962
Creator: Kikpatrick, M. E.; Bailey, D. M. & Smith, J. F.
Object Type: Article
System: The UNT Digital Library
SUMMARY OF HRT RUNS 22, 23 AND 24 (open access)

SUMMARY OF HRT RUNS 22, 23 AND 24

In runs 22, 23, and 24 the HRT was operated with downward flow through the core at powers up to 5 Mw. Because of leakage past the lower core tank patch, uranium could not be prevented from entering tbe blanket, so the concentration was deliberately kept above 1 g U/kg D/sub 2/O. The core power was about 0.6 of the total. Nuclear power fluctuations were larger than with upward core flow, and the cause was investigated intensively in run 22 at powers up to 1.8 Mw. Run 22 was terminated after 778 hours when a leak developed in a fuel feed pump weld. In run 23 the power was ratsed stepwise to 5 Mw. This run was terminated after 794 hours by the removal of the fuel, containing the fission and corrosion products accumulated in 10,028 hours of operation. Fuel replacement required three days. Run 24 operations were hampered by a leak which developed between the feed and letdown streams in the fuel letdown heat exchanger. The run was terminated after 546 hours, when a crack developed in a fuel feed line tee and leaked solution into the reactor cell. The changes in the core flow and heat transfer were …
Date: March 1, 1962
Creator: Bauman, H.F.; Buchanan, J.R.; Engel, J.R.; Haubenreich, P.N. & Richardson, D.M.
Object Type: Report
System: The UNT Digital Library
Simple High-Voltage Trapezoidal Pulse Generator (open access)

Simple High-Voltage Trapezoidal Pulse Generator

A description is given of a circuit used to produce negative voltage pulses up to 60 kilovolts with a portion rising with constart slope up to 10 kilovolts per microsecond. (auth)
Date: March 1, 1962
Creator: Gonella, L.
Object Type: Report
System: The UNT Digital Library
Radiochemistry of uranium (open access)

Radiochemistry of uranium

This volume which deals with the radiochemistry of uranium is one of a series of monographs on radiochemistry of the elements. There is included a review of the nuclear and chemical features of particular interest to the radiochemist, a discussion of problems of dissolution of a sample and counting technique, and finally, a collection of radiochemical procedures for the element as found in the literature.
Date: March 1, 1962
Creator: Gindler, J.E.
Object Type: Report
System: The UNT Digital Library
AN INTRODUCTION TO 704 FORTRAN (open access)

AN INTRODUCTION TO 704 FORTRAN

A fraction of the possibilities of Fortran are described, but at all times an effort was made to indicate where only a partial expose was made. Many specific examples are included to illustrate the word descriptions of Fortran programming. An appendix, which gives specific information concerning procedures relative to the use of the 704, is included. (auth)
Date: March 1, 1962
Creator: Pawlicki, G.S.
Object Type: Report
System: The UNT Digital Library
Eocr Control Rod Latch Reliability Test (open access)

Eocr Control Rod Latch Reliability Test

The final Vard design latch mechanism and hook for the EOCR Control Rod Drive Assembly was successfully and reliably operated in a hot organic medium containing particulates one hundred times the anticipated concentration in the EOCR and with a simulated heavy polymer deposition on all primary latch components. (auth)
Date: March 1, 1962
Creator: Burroughs, E. & Cohen, S.
Object Type: Report
System: The UNT Digital Library
MARITIME REACTOR PROGRAM ANNUAL PROGRESS REPORT FOR PERIOD ENDING NOVEMBER 30, 1961 (open access)

MARITIME REACTOR PROGRAM ANNUAL PROGRESS REPORT FOR PERIOD ENDING NOVEMBER 30, 1961

Progress is reported on general support of the NS Savannah, operation of the pressurized-water in-pile loop, and advanced core development. A shield survey, iodine adsorption studies, a bioassay development program, preparation of replacement control rod drives, irradiation testing of pressure-vessel steel, a thermal insulation investigation, and an analysis of primary system components for gamm-emitting elements were carried out in the NS Savannah program. Water- chemistry studies in the pressurized-water in-pile: loop were made to determine the specific activities and the chemical compositions of filterable and nonfilterable impurities in the loop water. Fuel development and irradiation tests and core I lifetime studies were carried out in the NS Savannah advanced core development. (M.C.G.)
Date: March 1, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
SPECTRAL SHIFT CONTROL REACTOR BASIC PHYSICS PROGRAM. EXPONENTIAL EXPERIMENTS AT ELEVATED TEMPERATURES ON LATTICES MODERATED BY D$sub 2$O-H$sub 2$O MIXTURES (open access)

SPECTRAL SHIFT CONTROL REACTOR BASIC PHYSICS PROGRAM. EXPONENTIAL EXPERIMENTS AT ELEVATED TEMPERATURES ON LATTICES MODERATED BY D$sub 2$O-H$sub 2$O MIXTURES

Results of exponential experiments conducted at elevated temperatures on rod lattices of slightly-enriched UO/sub 2/ moderated by D/sub 2/O-- H/sub 2/O mixtures are summarized. The fuel rods, 4%-enriched UO/sub 2/ swaged in stainless steel, were 0.476-inch OD by 0.016-inch wall. The non-moderator- tomoderator volume ratio was 1.006. The two moderator compositions studied were light water (0% D/sub 2/O) and a D/sub 2/O-H/sub 2/O mixture containing 81.5 mole% D/sub 2/O. The experimental facility and techniques are described. Material buckling values derived from radial and axial flux measurements are also summarized. (auth)
Date: March 1, 1962
Creator: Barrett, L.G.; Worsham, H.J. & Engelder, T.C.
Object Type: Report
System: The UNT Digital Library
Determination of Maximum Permissible Irradiation of Type 3 (SM-2) Fuel Plates (open access)

Determination of Maximum Permissible Irradiation of Type 3 (SM-2) Fuel Plates

Two methods were used for predicting the maximum permissible burnup in type 3 (SM-2) fuel plates: use of analytical models and use of existing irradiation data on UO/sub 2/ stainless steel dispersion fuel plates. Results with two analytical models indicated that burnups above 100% U/35 are permissible. Comparison of the expected burnup with available irradiation data indicates that successful performance of type 3 replacement cores in SM-1, SM-1A, and PM-2A can be expected. (auth)
Date: March 17, 1962
Creator: Wilder, A. S. & Lelleman, R. W.
Object Type: Report
System: The UNT Digital Library
Evaluation of Single and Dual Turbine-Generator Units for PL-3 (open access)

Evaluation of Single and Dual Turbine-Generator Units for PL-3

The investigation performed relative to the selection of a turbine- generator unit for the PL-3 portable nuclear power plant, Byrd Station, Antarctica, is described. Available conventional equipment was surveyed to minimize air shipment, installation, and cost requirements. Pertinent details of functional performance were considered. A comparison was drawn between the alternatives of utilizing either a single turbine generator unit shipped partially disassembled or twin, half-capacity units shipped assembled. The conclusion reached was that a single turbine-generator unit should be used with the turbine and generator shipped separately. (auth)
Date: March 1, 1962
Creator: Prall, T. F.
Object Type: Report
System: The UNT Digital Library
ORGANIC COOLANT REACTOR PROGRAM QUARTERLY REPORT, OCTOBER 1-DECEMBER 31, 1961 (open access)

ORGANIC COOLANT REACTOR PROGRAM QUARTERLY REPORT, OCTOBER 1-DECEMBER 31, 1961

Progress is reported on the organic-cooled reactor program under the topics: organic coolant research, EOCR experimental projects, and EOCR operations. Separate abstracts were prepared for each topic. (M.C.G.)
Date: March 30, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library

[BASEMENT BOX 67.0374]

Photograph three unidentified men walk through a field near a line of fire in the field. Smoke is rising next to where they are walking. one man is holding a coat and wearing a hat while the man behind him appears to be in a firemen's uniform. Caption: "High winds Tuesday afternoon fanned a grass fire at the Little Axe community east of here into a raging prairie blaze covering approximately two square miles."
Date: March 13, 1962
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Jose Greco]

Photograph of Jose Greco dancing on the North Texas campus in Denton. He is jumping in the air. He wears leather pants with embellishments, boots, and an open shirt with a vest. There is some light distortion around him.
Date: March 9, 1962
Creator: unknown
Object Type: Photograph
System: The UNT Digital Library

[Home Economics Meat Grinding Class]

Photograph of students in an industrial kitchen, grinding meat. One woman uses a machine while other students watch. This photograph was used in a brochure advertising the North Texas program in Home Economics.
Date: March 1962
Creator: unknown
Object Type: Photograph
System: The UNT Digital Library

[Home Economics Meat Grinding Class]

Photograph of students in an industrial kitchen, grinding meat. One woman uses a machine while other students watch. This photograph was used in a brochure advertising the North Texas program in Home Economics.
Date: March 1962
Creator: unknown
Object Type: Photograph
System: The UNT Digital Library

[Photograph 2012.201.B0240.0555]

Photograph taken for a newspaper owned by the Oklahoma Publishing Company. Caption: "A multi-million-dollar plant that will make components for missile, satellite and space vehicle electronic guidance systems will be built here by the General Electric Company."
Date: March 27, 1962
Creator: Gumm, John
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0244.0171]

Photograph taken for a newspaper owned by the Oklahoma Publishing Company. Caption: "The graves of Zack T. Miller and Jack Webb atop Cowboy Hill."
Date: March 9, 1962
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

BASEMENT BOX 67.0479

Photograph taken during daylight of wreckage destroyed by fire. Caption: "Only charred ruins remained Tuesday at the Herbert Caldwell home, NE 41 and Windsor Road, where three Caldwell children were burned to death Monday night."
Date: March 13, 1962
Creator: Lucas, Jim
Object Type: Photograph
System: The Gateway to Oklahoma History