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491 Matching Results
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THOREX PILOT PLANT: DECONTAMINATION RUN IX-16
None
Date:
April 18, 1956
Creator:
Walker, J.H. & Sadowski, G.S.
Object Type:
Report
System:
The UNT Digital Library
Boundary-Layer-Transition and Heat-Transfer Measurements from Flight Tests of Blunt and Sharp 50 Degree Cones at Mach Numbers from 1.7 to 4.7
Boundary-layer-transition and heat-transfer measurements were obtained from flight tests of blunt and sharp cones having apex angles of 50 deg. The test Mach number range was from 1.7 to 4.7, corresponding to free-stream Reynolds numbers, based on cone base diameter, of 18. 3 x 10(exp 6) and 32.1 x 10(exp 6), respectively. Transition on both models occurred at a local Reynolds number of 1 x 10(exp 6) to 2 X 10(exp 6) based on distance from the stagnation point. Transition Reynolds numbers based on momentum thickness were between 320 and 380 for the blunt cone. The model surface roughness was 25 rms microinches or greater. Turbulent heat transfer to the conical surface of the blunt cone at a Mach number of 4 was 30 percent less than that to the surface of the sharp cone. Available theories predicted heat-transfer coefficients reasonably well for the fully laminar or turbulent flow conditions.
Date:
April 18, 1957
Creator:
Chauvin, Leo T. & Speegle, Katherine C.
Object Type:
Report
System:
The UNT Digital Library
Heat Transfer and Boundary-Layer Transition on a Highly Polished Hemisphere-Cone in Free Flight at Mach Numbers Up to 3.14 and Reynolds Numbers Up to 24 X 10(Exp 6)
"A highly polished hemisphere-cone having a ratio of nose radius to base radius of 0.74 and a half-angle of 14.5 degrees was flight tested at Mach numbers up to 4.70. Temperature and pressure data were obtained at Mach numbers up to 3.14 and a free-stream Reynolds number of 24 x 10(exp 6) based on body diameter. The nose of the model had a surface roughness of 2 to 5 microinches as measured with an interferometer" (p. 1).
Date:
April 18, 1957
Creator:
Buglia, James J.
Object Type:
Report
System:
The UNT Digital Library
Heat-Transfer and Pressure Distribution on Six Blunt Noses at a Mach Number of 2
Report presenting testing on six blunt-nose models at angles of attack ranging from 0 to 5 degrees in order to evaluate the heat transfer and pressure on their surfaces. Information about transition, proper design, and locations of greatest and least heat transfer is provided.
Date:
April 18, 1957
Creator:
Carter, Howard S. & Bressette, Walter E.
Object Type:
Report
System:
The UNT Digital Library
Measurements of Heat Transfer and Boundary-Layer Transition on an 8-Inch-Diameter Hemisphere-Cylinder in Free Flight for a Mach Number Range of 2.00 to 3.88
"Measurements of aerodynamic heat transfer have been made along the hemisphere and cylinder of a hemisphere-cylinder rocket-propelled model in free flight up to a Mach number of 3.88. The test Reynolds number based on free-stream condition and diameter of model covered a range from 2.69 x l0(exp 6) to 11.70 x 10(exp 6). Laminar, transitional, and turbulent heat-transfer coefficients were obtained" (p. 1).
Date:
April 18, 1957
Creator:
Garland, Benjamine J. & Chauvin, Leo T.
Object Type:
Report
System:
The UNT Digital Library
Some Effects of Heat Transfer at Mach Number 2.0 at Stagnation Temperatures Between 2,310 and 3,500 Degrees R on a Magnesium Fin With Several Leading-Edge Modifications
Report presenting testing of four models of a thin magnesium fin, with the leading edge swept back 35 degrees, of a type used to stabilize the first stages of rocket-propelled multistage hypersonic models. The investigation was carried out to determine some effects of aerodynamic heating at high stagnation temperatures on the leading edges of fins and to determine the relative effectiveness of several leading-edge protective methods. The fins tested included a basic fin, a fin with a blunt leading edge, a fin with a blunt leading edge wrapped with Inconel, and a fin with a blunt leading edge made of stainless steel.
Date:
April 18, 1957
Creator:
Bland, William M., Jr. & Bressette, Walter E.
Object Type:
Report
System:
The UNT Digital Library
Blending UNH streams of different uranium enrichments
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.
Object Type:
Report
System:
The UNT Digital Library
Direct Maintenance Practices for the Homogeneous Reactor Test
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 shielding water are described. Estimates of shutdown times and costs of tools and spare parts are presented also. (auth)
Date:
April 18, 1958
Creator:
Beall, S. E. & Jurgensen, R. W.
Object Type:
Report
System:
The UNT Digital Library
Some Nuclear Characteristics of Spherical Double-Blanket Reactors
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 inner or outer blanket region contains 4000 g Th/liter as ThO/sub 2/ slurry in D/sub 2/O while the other blanket region holds thorium concentrations of 0, 500, or 1000 g Th/liter. The effects of introducing an 8% poison fraction into the core and 3 g U/syo 233/kg Th into the blanket are examined individually. It is found that reactivity effects are negligible if the inner blanket contains 4000 g Th/liter and settling occurs in the dilute outer region. On the other hand. for a concentrated outer blanket, large reactivity additions are to be expected on removing the thorium from the dilute inner region. Some fuel and thorium inventory reductions appear possible …
Date:
April 18, 1958
Creator:
Tobias, M. & Fowler, T.B.
Object Type:
Report
System:
The UNT Digital Library
THE DIFFUSION OF RADIOACTIVE FISSION PRODUCTS FROM POROUS FUEL ELEMENTS
The release of fission products from porous fuel elements during irradiation may be largely a diffusion process. An equivalent-sphere hypothesis was proposed to provide a model by which the diffusion can be analyzed. The equations of diffusion were previously solved for in- pile conditions. The slow convergence of the formulas makes the previous solutions awkward. In the present investigation alternate formulas were derived which are more suitable under certain circumstances. Tables were prepared from which release rates and accumulations may be evaluated for prescribed conditions. The application of the analysis to the interpretation of release data is explained. (auth)
Date:
April 18, 1960
Creator:
Beck, S.D.
Object Type:
Report
System:
The UNT Digital Library
Equations of State for Stream-Water Mixtures and Some Representative Applications Analysis
The majority of two-phase flow problems involving equations of state are solved by use of point-wise utilization steam table values. In this manner, problems involving the use of the various flow equations of continuity, momentum and energy are generally forced into iterative solutions. Considerable effort towards the development of an analytical expression for the state equation seems indicated so as to simplify the analysis of two-phase problems, particularly the transient cases. The question of instability of state and mixture condition is particularly apparent in the analysis of systems undergoing phase transformation as demonstrated by the significant difference between simple theory and experimental critical flow determinations. The assumption of homogeneous, equilibrium mixtures is indicated as a first attack upon the problem.
Date:
April 18, 1960
Creator:
Love, W. J.
Object Type:
Report
System:
The UNT Digital Library
Increased production study B, D, DR, F, H and C reactors
This document studies a broad study program which is currently in progress in Irradiation Processing Department to evaluate the technical and economic feasibility of various methods of obtaining increased production from the six older reactors (B, D, DR, F, H, and C Reactors). Due to time limitations this study has been in general terms only, but has indicated that considerable increased plant return can be obtained from an increased conversion ratio as well as from higher reactor power levels. The work performed by this Unit has been concerned with defining the reactor process component modifications, and process piping changes between the 105 Building valve pits and effluent basins which will be required to attain the production increases.
Date:
April 18, 1960
Creator:
Fifer, N. F. & Kempf, F. J.
Object Type:
Report
System:
The UNT Digital Library
Partial modification of 190-KW pump No. 1, Project CGI-883: Increased process water flow, 100 K
The 190-KW process water pumping Unit No. 1 is scheduled to be modified for increased pumping capacity under Project CGI-883- Component parts for this modification are expected to-be received during June 1960. Installation of these components would require approximately ten days; due mainly to grinding of the high lift pump case to make room for the new larger diameter impeller. In order to minimize lost production, it has been proposed by K Reactor Operation that the high lift pump be modified early this spring during the scheduled maintenance overhaul period on pumping unit No. 1. The test impeller recently removed from the No. 1 high lift pump in KE would be repaired and installed in the KW pump at this time. Later, in June or July when the components for the complete modification are available the low-lift pump and drive motor would be modified and associated electrical and instrument alterations would be completed during a normal reactor outage. Adoption of the proposed plan would make it necessary to operate the modified high lift pump for a period of approximately three months with an unmodified low-lift pump. A study was made to determine the feasibility of operating the pumping unit in …
Date:
April 18, 1960
Creator:
Schack, M. H.
Object Type:
Report
System:
The UNT Digital Library
STUDY OF THE BETA TREATMENT OF URANIM. Progress Report to the Oak Ridge Operations Office for the Period November 1, 1959-April 1, 1960
Activities in a program to determine the effects of product size (or dimensions), composition, and heat treatment on beta-treated U are reported. Progress to date was chiefly confined to organizing the program and setting up equipment. A Jominy end-quench apparatus was constructed, and preliminary experiments were run on as-cast metal to test the Jominy-oscillographthermocouple system. Results are tabulated. The method to be used for characterization of beta-treated samples by determination of growth index and texture is also described. (J.R.D.)
Date:
April 18, 1960
Creator:
Russell, R.B.
Object Type:
Report
System:
The UNT Digital Library
EXCAVATION OF CONTAINED TNT EXPLOSIONS IN TUFF
The effects of two contained H. E. explosions in volcanic tuff were examined by mining directly into the explosion sites. Ore explosion (516 lb of TNT) increased its initial shot chamber volume of about 9 cu ft by a factor of sbout 5 and produced in addition some 126 cu ft of broken rock. Around this explosion, only natural joints in one direction were filled with carbon to a maximum distance of 42 ft, and no new fractures in other directions were developed. The other explosion (973 lb of TNT) expanded its 17 cu ft chamber to 10 times this initial volume and led to rock breakage, mostly by subsequent roof collapse, of 345 cu ft. Because this shot vented on firing, very little of the carbon-carrying gases entered joints, and fractures caused by the explosion are almost absent. The features characteristic of these two explosions were compared to an earlier 1000-lb explosion in salt in which, by contrast, numerous radial carbon-filled cracks were produced, and the less expanded chambers survived without collapse. For the explosions in tuff it was concluded that joints exercised a primary role in locating the surfaces of fracture failure, early venting inhibits development of carbon-marked …
Date:
April 18, 1961
Creator:
Short, N.M.
Object Type:
Report
System:
The UNT Digital Library
Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor
Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.
Date:
April 18, 1961
Creator:
Cherubini, J. H.; Beaver, R. J. & Leitten, C. F., Jr.
Object Type:
Report
System:
The UNT Digital Library
Observations on the Response of a Lithium-Drifted Detector Protons
The response of a lithium-drifted solid state detector was measured for protons and found to be linear up to the highest energy observed, 13.2 Mev. The resolution observed for these protons is 0.81% with a bias of 500 volts and 0.65% with a bias of 250 volts. (auth)
Date:
April 18, 1961
Creator:
Benveniste, J.; Booth, R. & Mitchell, A. C.
Object Type:
Report
System:
The UNT Digital Library
Thermodynamic Data for Water
Thermodynamic data for liquid and gaseous water were compiled and extended to limits of pressure and temperature imposed by Hugoniot, adiabat, and Thomas-Fermi model considerations. The internal energy variation is discussed. (auth)
Date:
April 18, 1961
Creator:
Howard, J. C.
Object Type:
Report
System:
The UNT Digital Library
Budget Estimate for Fiscal Year 1964
The stated objective of the SNAP-50 reactor and primary system development program is the design, fabrication, development and test operation of a series of reactors and associated equipment leading to a fully qualified and accepted SNAP-50 flight reactor and primary system.
Date:
April 18, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Calculation of Departure From Nucleate Boiling Conditions for the Spert Iii Reactor in the High Pressure Region
Calculations are made to determine the safe steadystate power operating limits of the Spert III reactor from the viewpoint of fuel plate burnout. A computer program is developed for the IBM 704 to aid in these calculations. The Bettis design departure from nucleate boiling (DNB) equation is used in conjunction with the LeTourneau and Grimble method of hot channel'' analysis in the development of the calculations. For cases where DNB occurs in the bulk boiling region, a modified Martinelli-Nelson twophase flow correlation and some experimental singlephase pressure drop data are employed. DNB for a typical operating condition of 550 deg F inlet temperature and 2500 psig is computed to check the code. The results of the sample calculation show that at a steady- state power level of 60 Mw (maximum design power) the minimum flow rate required to prevent DNB is approximately 8000 gpm. (auth)
Date:
April 18, 1962
Creator:
Dugone, J.
Object Type:
Report
System:
The UNT Digital Library
A R.F. Vernier Time to Pulse Height Converter
This technical report describes a pulse height converter that employs the R.F. vernier method. This particular converter has been developed for use with the pulsed beam facility of the BNL Van de Graaff. This report then details a number of tests of the converter made using a RIDL model 34-12, 400-channel analyzer. The report includes 6 figures and 4 circuit diagrams to accompany the findings.
Date:
April 18, 1962
Creator:
Lowe, J.
Object Type:
Report
System:
The UNT Digital Library
RADIOISOTOPES AND RADIATION APPLICATIONS. Quarterly Progress Report No. 12
Continued research is reported in the areas of intrinsic radioactive tracers for industrial process control and the effects of structural factors on radioinduced graft polymerization. The use of Be-- Po neutron sources for production of short-lived isotopes is being investigated. Data are included on the effects of target volume, high-Z scattering media, target-isotope concentration, and macroscopic cross-section on speciflc and total activation produced with a 10-curie source. Research on graft-polyerization concerning the effects of structure on freetinued. Results indicate that the radical formed in a variety of substituted methacrylate polymers is the same in all cases. (J.R.D.)
Date:
April 18, 1962
Creator:
Sunderman, D.N. ed.
Object Type:
Report
System:
The UNT Digital Library
Texas Attorney General Opinion: WW-1314
Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether it is lawful for a nineteen year old boy, who has had his disabilities removed under Article 5921, V.C.S., to possess or consume any alcoholic beverages in any public place under the provisions of Article 666-17 (14)(a), V.C.S., and whether a minor whose disabilities have been removed can be appointed a notary public and related questions.
Date:
April 18, 1962
Creator:
Texas. Attorney-General's Office.
Object Type:
Text
System:
The Portal to Texas History
C reactor overbore fuel examination
On April 16, 1962, the fuel charge in overbore tube 3062-C sustained a failure, and upon examination after discharge was found to contain three split failures and three ``worm tracked`` elements (depression in the aluminum cladding apparently the result of uranium cleavage and subsequent yielding of the cladding). These failures occurred approximately ten days following a period of reactor neutron flux cycling, and during a second cycle at C Reactor. In addition to the failures, a total of 17 elements, from nine separate fuel charges, contained worm tracks. Four of these elements were sent to Radiometallurgy Laboratory for destructive examination, to determine the mechanism of the suspected uranium cleavage.
Date:
April 18, 1963
Creator:
Hladek, K. L.; Teats, R. & Weakley, E. A.
Object Type:
Report
System:
The UNT Digital Library