44 Matching Results

Search Results

Results: 1 - 24 next
open access

NACA Conference on High-Speed Aerodynamics: A Compilation of Papers Presented

Description: A reproduction of the technical papers presented by staff members of the NACA Laboratories at the NACA Conference on High-Speed Aerodynamics at the Ames Aeronautical Laboratory during March 18-20, 1958. The primary purpose of the conference was to convey to military services and contractors the results of recent research and to provide an opportunity to discuss the results.
Date: 1958-03-18/1958-03-20
Partner: UNT Libraries Government Documents Department
open access

Effects of preheat time in compound layer formation

Description: Hanford fuel elements are made by brazing uranium cores in aluminum cans. The interface, or junction, between the AlSi braze and uranium core known as the compound layer, is composed of an intermetallic complex. The properties of this compound layer, brittleness, ductility, toughness, are considered to have a pronounced influence on the performance of fuel elements in the reactors. This report presents the results of initial efforts to identify the compound layers and establish some of the proc… more
Date: August 18, 1958
Creator: Strand, C. A. & Padgett, E. V.
Partner: UNT Libraries Government Documents Department
open access

Production Test IP-98-I revised tube charge pattern for graphite annealing: Interim Report

Description: Graphite shrinkage of 0.60 inches (approximately 30 per cent) has been observed at F Reactor in the region of maximum graphite distortion. A reduction of graphite distortion at B Reactor of 0.60 inches in the top-center and 0.32 inches in the top-far region also has been observed. Analysis of the vertical traverse data indicates that continued graphite annealing with resultant decrease in graphite distortion might be anticipated although perhaps at a reduced rate. No significant detrimental eff… more
Date: December 18, 1958
Creator: Graves, S. M.
Partner: UNT Libraries Government Documents Department
open access

Blending UNH streams of different uranium enrichments

Description: The cost and feasibility of blending UNH streams of different uranium enrichments at HAPO was evaluated on a preliminary basis. Cases studied were blending 37.5% enriched UNH with depleted E metal UNH to yield a 0.947% enriched end product, and blending depleted E metal UNH with the depleted natural uranium to yield 0.7115% enriched end product. A reasonable degree of feasibility is indicated for such a blend program at HAPO.
Date: April 18, 1958
Creator: Campbell, B. F.
Partner: UNT Libraries Government Documents Department
open access

Transformation Kinetics of Plutonium. Part 2. A Study of the Gamma to Beta to Alpha and Alpha to Beta to Gamma Transformations

Description: The kinetics of the gamma deg C was con- beta deg C was con- alpha , beta deg C was con- gamma , and alpha deg C was con- beta deg C was con- gamma transformations were determined with a fiuid displacement technique. The rates of formation of the alpha and beta phases from the gamma phase were determined after gamma heat treating and allowing a sample to traasform isothermally in the alpha and beta ramges. Isothermal reaction curves were obtained from 160 C to -78C. The time-temperature-transfo… more
Date: July 18, 1958
Creator: Nelson, R. D.
Partner: UNT Libraries Government Documents Department
open access

SHIELDING-RESEARCH AREA AT BATTELLE

Description: The design and constructlon of the shielding facility at Battelle are described. This facility consists of an open pool with a fission plate, an instrument bridge and tower, a control room, and radiation-detection instruments. The shielding pool is located at the end of the thermal column of the Battelle Research Reactor (BRR). The fission plate is 28 in. in diameter and contains approximately 3.5 kg of U/sup 235/. The plate was fabricated from three pieces of highly enriched U and clad with ab… more
Date: September 18, 1958
Creator: Morgan, W.R.; Epstein, H.M.; Anno, J.N. Jr. & Chastain, J.W. Jr.
Partner: UNT Libraries Government Documents Department
open access

STUDIES OF UPPER-PLENUM COOLANT CIRCULATION IN A QUARTER-SCALE AIR-FLOW MODEL OF THE PWR

Description: Air-flow studies were run in a quarter-scale flow model of the PWR to determine distribution of flow throughout the upper-plenum region with two different hold-down-barrel designs. With each hold-down barrel, flow paths were determined for operation with four loops, three loops, two opposed loops, and two adjacent loops. Exploration of flow patterns and velocities throughout the upper plenum showed that circulation of coolant throughout the upper plenum was satisfactory with either of the hold-… more
Date: March 18, 1958
Creator: Orban, A.R. & Hazard, H.R.
Partner: UNT Libraries Government Documents Department
open access

METALLOGRAPHIC EXAMINATION OF COMPONENTS AND COUPONS FROM HRP IN-PILE LOOP L-2-17-PART I

Description: Metullographic examinations of representative reactor components and coupons from HRP in-pile loop L-2-l7 are reported. The loop operated for a total of 1l36.8 hours at 300 deg C in beam hole HB-2 of the LITR. The results are discussed and tabulated. Photographs are also included. (J.R.D.)
Date: February 18, 1958
Creator: Richt, A.E.
Partner: UNT Libraries Government Documents Department
open access

Simulation of the Orsort Buttermilk Reactor, Loss of Fuel Flow

Description: The study of the Oak Ridge School of Reactor Technology Buttermilk Reactor is continued with analog computer simulation of a loss of fuel flow incident. (T-R-H-)
Date: July 18, 1958
Creator: Walker, C. S.
Partner: UNT Libraries Government Documents Department
open access

CHEMICAL INDICATIONS OF HRT MISBEHAVIOR IN RUN 17-A

Description: The cause and significance of the changes in chemical composition of the HRT fuel and changes in reactivity during operation, particularly in run 17A, were investigated. It was concluded that a rise in reactor power level causes deposition of U, Cu, and Ni in some hydrolytic process within the core circulation system in a region which is at a position between zero and average nuclear importance. The deposition requires several minutes to several hours and is relatively easily reversiable when t… more
Date: September 18, 1958
Creator: McDuffie, H.F.
Partner: UNT Libraries Government Documents Department
open access

Status of Subcontract Work on Effects of Radiation on Solvent Extraction Processes

Description: The results of the Stanford Research Institute studies of the effects of radiation on solvent extraction processes are summarized, and a desirable direction for future work is indicated. Studies performed to date have shown that: (1) nearly all of the irradiation-induced increase in time required for TBP- -Amsco--aqueous phase separation is due to formation of a polymer, of unknown chemical structure; (2) uranium retention by the TBP-- Amsco phase during stripping operations is due approximatel… more
Date: June 18, 1958
Creator: Davis, W., Jr.
Partner: UNT Libraries Government Documents Department
open access

MOLTEN SALT HEAT TRANSFER

Description: The experimental system used in the determination of turbulent forced- convection heat-transfer coeificients with molten salts is described, and the results of the experimental program are detailed. The salts studied have been the mixtures NaNO/sub 2/-NaNO/sub 3/--KHO/sub 3/, LiF --NaF --KF and s with the LiF--NaF-KF mixture in Inconel tubes are explained in terms of an interfacial film. A nonwetting phenomenon is postulated to describe the decreased heat transfer in the NaF--ZrF/sub 4/-UF/sub … more
Date: February 18, 1958
Creator: Hoffman, H.W.
Partner: UNT Libraries Government Documents Department
open access

Measurements Through a Hot Cell Window Using Optical Tooling

Description: S>Optical tooling has been evaluated for the measurement of physical dimensions of radioactive parts through hot cell windows. Instruments were set up outside of a four foot thick lead glass window and by means of a grid plate which had been accurately scribed, a ''contour map'' or calibration chart of the window variations was recorded. Although the window was not specially selected, the readings were within 1.0% of the true dimension without using correction factors. One of the calibration ch… more
Date: July 18, 1958
Creator: Abbatiello, A. A.
Partner: UNT Libraries Government Documents Department
open access

Investigation of Two Bluff Shapes in Axial Free Flight Over a Mach Number Range From 0.35 to 2.15

Description: Report presenting testing of a fineness-ratio-2.71 right circular cylinder and a fineness-ratio-4.0 circular cylinder with a rounded nose and flared afterbody over a range of Mach and Reynolds numbers. Time histories, cross plots of force coefficients, rolling velocity, and longitudinal-force coefficient are provided for the two cylinders.
Date: March 18, 1958
Creator: Coltrane, Lucille C.
Partner: UNT Libraries Government Documents Department
open access

Experimental Behavior of Pentaborane-Air Combustion Products During Expansion in a Convergent Divergent Nozzle

Description: "In order to evaluate the post combustion behavior of boric oxide, pentaborane-air mixtures, burned to completion at a combustor pressure of 3 atmospheres, were expanded through a 7.1-inch-long convergent-divergent nozzle having a 4-inch-diameter throat and an exit-to-throat area ratio of 1.68. The experimentally determined thrust performance was in good agreement with the ideal equilibrium performance at stagnation temperatures of 3300 deg R and lower. The boric oxide vapor at the combustor ex… more
Date: February 18, 1958
Creator: Branstetter, J. Robert & Setze, Paul C.
Partner: UNT Libraries Government Documents Department
open access

Direct Maintenance Practices for the Homogeneous Reactor Test

Description: The Homogeneous Reactor Test is designed for maintenance to be performed while the parts of the reactor are partinlly or completely submerged in water to reduce radiation levels. Tools with long handles permit the operator, standing above the equipment, to disconnect flanged joints, air lines, electrical and instrument leads, etc., in a minimum time. The techniques and tools employed to accomplish these various operations and to minimize intermixing of the contaminated process fluids with the s… more
Date: April 18, 1958
Creator: Beall, S. E. & Jurgensen, R. W.
Partner: UNT Libraries Government Documents Department
open access

ELECTROLYSIS CELL FOR RECOMBINATION STUDIES

Description: A small, laboratory-sized loop was designed for steady-state radiolytic gas recombination studies. It consists of an electrolysis cell, which simulates the radiolytic gas formed in a reactor, and a bomb for containing slurry under test. The electrolysis capacity of the system is adequate for the study of slurries having recombination rates as high as 10 moles/hr/liter of slurry at the proposed slurry reactor operating conditions. (auth)
Date: September 18, 1958
Creator: Culver, R.S.
Partner: UNT Libraries Government Documents Department
open access

PROPOSAL FOR AN EXPERIMENTAL STUDY OF THERMAL GRADIENT MASS TRANSFER IN A THERMAL CONVECTION LOOP

Description: S>A proposal is presented to design, construct, and operate a thermal gradient mass transfer loop to provide data on rates of solution and deposition as functions of time. Operation of the hot solution zone under controlled isothermal conditions is planned. It is felt that data obtained in such a loop would be of value in assessing the validity of presently proposed mecharisms for thermal gradient transfer or in devising new ones. The thermal and forced convection loops appear to offer moat pro… more
Date: February 18, 1958
Creator: Prados, J.W. & Scott, J.L.
Partner: UNT Libraries Government Documents Department
open access

PHASE III-FOREIGN REACTOR-FUEL SAMPLE IRRADIATION OF U$sub 3$O$sub 8$-Al DISPERSIONS. IRRADIATION REQUEST ORNL-MTR-35

Description: The integrity and suitability of 35 vol.% U/sub 3/ O/sub 8/ dispersion in Al as a fuel for foreign reactors were determined. The fuel was exposed in the beryllium reflector of the MTR. Sample fabrication and conditions of exposurne are described, and the results are tabulated. (J.R.D.)
Date: October 18, 1958
Creator: Leitten, C.F. & Kucera, W.J.
Partner: UNT Libraries Government Documents Department
open access

Some Nuclear Characteristics of Spherical Double-Blanket Reactors

Description: A number of cases were studied to determine some of the nuclear characterlstics of double-blanket reactors. The reactor geometry is spherical. the average temperature is 280 deg C the core ID is 4 ft and the pressure vessel ID is 9 ft in all cases. The core is contained in a 1/2-in. Zircaloy tank, while the blanket is divided into two regions by another another 1/2-in. Zircaloy shell. The region adjacent to the core is either 0.5 or 1-ft thick Comparison is made of reactors in which either the … more
Date: April 18, 1958
Creator: Tobias, M. & Fowler, T.B.
Partner: UNT Libraries Government Documents Department
open access

Tabular Summary of Zircaloy-2 in-Pile Rocking Autoclave Corrosion Data

Description: A tabular resume of the data from 37 in-pile Zircaloy-2 rocking autoclave corrosion experiments performed since August 1954 is presented. Included are data concernin,; solutions used on the specimens before and after the reactor eKposure, sample treatment prior to irradiation conditions during exposure, data on oxygen consumption and specimen weight losses, and miscellaneous data. (J.R.D.)
Date: June 18, 1958
Creator: Davis, R.J.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen