AIRBLAST OVERPRESSURE AND DYNAMIC PRESSURE OVER VARIOUS SURFACES (open access)

AIRBLAST OVERPRESSURE AND DYNAMIC PRESSURE OVER VARIOUS SURFACES

Static overpressure and dynamic pressure versus time over surfaces processing different physical properties were measured on two tower shots, 6 and 12. On Shot 12, three surfaces were provided: the natural desert, a water surface consisting of a flooded area, and an asphalt surface. On Shot 6, desert and asphalt areas only were available. There were 123 channels of instrumentation installed for Shot 12, and 24 for Shot 6. From the data, a system of wave-form classification was devised for overpressure and dynamic-pressure- versus-time measurements. Incorporation of this system into data analysios indicates that it is possible for an ideal peak pressure to be identified with a nonideal wave form. Introducing both variables, wave form and peak pressure, into analyses reduces ambiguioties associoated with comparing results of different nuclear tests. The data show the effect of the nature of the surface upon airblast phenomena from a nuclear explosion. The effects of surface conditions upon shock phenomena are made more understandable by a review of temperature computatioons, using shock wave parameters in addition to an analysis based upon the arrioval time of the thermal pulse. A phenomenological discussion of precursor formation is presented, and comparisons are made using data from all …
Date: September 11, 1957
Creator: Sachs, D. C.; Swift, L. M. & Sauer, F. M.
System: The UNT Digital Library
CALCULATION OF SHIELD INDUCED GAMMA RADIATION ESCAPING THROUGH OPENINGS IN A BIOLOGICAL SHIELD--APPLICATION TO THE HRT (open access)

CALCULATION OF SHIELD INDUCED GAMMA RADIATION ESCAPING THROUGH OPENINGS IN A BIOLOGICAL SHIELD--APPLICATION TO THE HRT

None
Date: January 11, 1957
Creator: Claiborne, H.C. & Fowler, T.B.
System: The UNT Digital Library
CHARACTERIZATION OF INCLUSIONS IN DINGOT URANIUM (open access)

CHARACTERIZATION OF INCLUSIONS IN DINGOT URANIUM

The nonmetallic inclusions in both as-reduced and fabricated dingot U were studied for comparison with those in ingot U. Special attention was paid to the hydride for the purpose of determining the amount and distribution in the various types of U. The types and distribution of other inclusions were also studied. It wss found tbat the dingot U was of a higher quality than ingot U and was comparable to as-reduced derby U on the basis of over-all inclusion count. The H content in dingot U, however, was found to be appreciably higher than in either ingot or derby U. (auth)
Date: January 11, 1957
Creator: Cheney, Donald M. & Dickerson, Ronald F.
System: The UNT Digital Library
Comparison of the Corrosion Resistance of Some High-Nickel Content Brazing Alloys to Fuel Compositions 44 and 107 (open access)

Comparison of the Corrosion Resistance of Some High-Nickel Content Brazing Alloys to Fuel Compositions 44 and 107

Non-chromium bearing brazing alloys containing large percentages of nickel (89 to 93 wt%) show good corrosion resistance to the NaF-KF-LiF-UF{sub 4} (11.2-41.0- 45.3-2.5 mole %, fuel 107) mixture at 1500{degrees}F under seesaw-test conditions. Corrosive action by fuel 107 was greater than that by NaF-ZrF{sub 4}-UF{sub 4} (53.5-40.0- 6.5 mole %, fuel 44) mixture on nickel-base brazing alloys tested.
Date: October 11, 1957
Creator: Manly, W. D.
System: The UNT Digital Library
CONTROL SYSTEM FOR HRT COOLING WATER (open access)

CONTROL SYSTEM FOR HRT COOLING WATER

None
Date: February 11, 1957
Creator: Moore, R.L.
System: The UNT Digital Library
Conversion Chemistry of Plutonium Nitrate (open access)

Conversion Chemistry of Plutonium Nitrate

This report addresses the conversion chemistry of plutonium nitrate.
Date: April 11, 1957
Creator: Harmon, K. M. & Reas, W. H.
System: The UNT Digital Library
Cross Sections for Ocusol-a Program (open access)

Cross Sections for Ocusol-a Program

None
Date: June 11, 1957
Creator: Roberts, J. T. & Alexander, L. G.
System: The UNT Digital Library
CURVE PLOTTING ROUTINE FOR THE ORACLE (open access)

CURVE PLOTTING ROUTINE FOR THE ORACLE

None
Date: April 11, 1957
Creator: Lietzke, M.P.
System: The UNT Digital Library
Equipment design scope conversion of 313 to I & E production (open access)

Equipment design scope conversion of 313 to I & E production

Equipment required to provide production capacity of 525 tons per month of I & E fuel elements ``O,`` ``C,`` and ``K`` sizes in the 313 Building is specified in this document.
Date: February 11, 1957
Creator: Drumheller, K.
System: The UNT Digital Library
Evaluation of Container Materials for Zircex and Darex Nuclear-Fuel- Recovery Processes (open access)

Evaluation of Container Materials for Zircex and Darex Nuclear-Fuel- Recovery Processes

The selection of a suitable material for the processing equipment is most important in fuel-recovery processes. The problem arises because of the aggressive nature of the reagents that must be used for disintegrating or dissolving some spent fuel elements. In this investigation, corrosion tests were made under conditions simulating those that may occur in several proposed processes in order that candidate materials of construction could be evaluated. No material has been found which would allow both the hydrochlorination and dissolution steps of the vapor-phase Zircex process to be carried out in a single vessel. For a two-vessel process, several materials, please delete the above abstract no. 4811================
Date: December 11, 1957
Creator: Miller, P. D.; Peterson, C. L.; White, E. L. & Fink, F. W.
System: The UNT Digital Library
Evaluation of Reactor Core Materials for a Gas-Cooled Reactor Experiment (open access)

Evaluation of Reactor Core Materials for a Gas-Cooled Reactor Experiment

An evaluation of core materials for a gas-cooled reactor is being made. Work on the ZrH/sub n/ moderator has been confined to the high-hydrogen or delta- phase material. Methods for preparing sound hydride bodies of the highhydrogen composition have been developed. Both solid hydride and hydride powder compacts are being clad by a pressure-bonding technique. The hot hardness, tensile strength, thermal conductivity, thermal-expansion coefficient, and dissociation pressure of the delta-phase material are being determined. Control-material development was directed at rare-earth-oxide dispersions in Ni-chrome V or Co alloys. The reference fuel element is dispersedUO/sub 2/ in stainless steel. Studies include work on fabrication techniques and irradiation damage, and physical- and mechanical-property determinations. Several alternate fuels are being investigated. Gas-coolant studies involve N-metal and NH/sub 4/-metal reactions. Several additives to retard nitriding are being investigated. An in- pile-loop facility for testing reference materials is being constructed for operation in the Battelle Research Reactor. (auth)
Date: July 11, 1957
Creator: Keller, D. L.
System: The UNT Digital Library
Non-Symmetrical Main Coolant System Analysis (Nomacs). Part I (open access)

Non-Symmetrical Main Coolant System Analysis (Nomacs). Part I

Non-symmetrical main coolant system analysis is an IBM-704 digital program for calculating the reactor generation, primary coolant temperature distribution, and steam temperature, pressure, and flow to the main and auxiliary turbines during a transient period. The program represents a system composed of a two-pass high pressure water cooled reactor ivith tivo main primary coolant loops each having its own steam generator, separator, and drum. The generated steam from each loop is piped into a common header which is then piped to the main and auxiliary turbines and other steam loads in the system. The mathematical representation for solution is described. (M.H.R.)
Date: September 11, 1957
Creator: Larsen, R.C.
System: The UNT Digital Library
Pilot Plant Studies of Atmospheric and Pressure Leaching of Uranium Ores in Alkaline Solutions (open access)

Pilot Plant Studies of Atmospheric and Pressure Leaching of Uranium Ores in Alkaline Solutions

None
Date: June 11, 1957
Creator: Beverly, R. G.; Millsap, W. A. & Winslow, G.
System: The UNT Digital Library
A PRELIMINARY STUDY OF PRE-SOLVENT EXTRACTION TREATMENT OF STAINLESS STEEL- URANIUM FUELS WITH DILUTE AQUA REGIA (open access)

A PRELIMINARY STUDY OF PRE-SOLVENT EXTRACTION TREATMENT OF STAINLESS STEEL- URANIUM FUELS WITH DILUTE AQUA REGIA

The continuous dissolution of 304 stainless steel and stainless steel - UO/sub 2/ alloy in dilute aqua regia was studied with subsequent stripping of the dissolver product to remove chloride ion. The process has the advantage of producing, by means of a simple head end treatment, a solvent extract feed in a conventional nitric acid medium so that existing solvent extraction processes, materials of construction and waste disposal methods can be used. The purposes of this study were to investigate the the variables affecting the dissolution process and to obtain dissolver scale-up data, and to investigate the removal of chloride from the dissolver product and the variables affecting the stripping operation. A continuous flooded pot dissolver was used. It has the advantages of stability of operation and ease of control in comparison with column dissolvers and requires a minimum of mechanical processing prior to dissolution. Stripping of the dissolver prcduct to remove chloride ion was studied in a 4-in. diameter Pyrek bubblecap column containing 12 single babble cap plates. Continuous dissolution rates and dissolver product stainiess steel loadings were correlatsd with aqua regla feed composition, acid feed rats and surface area exposed to reaction. Profiles of chloride concentration down the …
Date: October 11, 1957
Creator: Kitts, F.G. & Perona, J.J.
System: The UNT Digital Library
PROPERTIES OF BERYLLIUM OXIDE AND CARBIDES OF BERYLLIUM, MOLYBDENUM, NIOBIUM, TANTALUM, AND TITANIUM (open access)

PROPERTIES OF BERYLLIUM OXIDE AND CARBIDES OF BERYLLIUM, MOLYBDENUM, NIOBIUM, TANTALUM, AND TITANIUM

None
Date: February 11, 1957
Creator: Weber, William P.; Quirk, John F.; Lemmon, Alexis W., Jr. & Filbert, Robert B., Jr.
System: The UNT Digital Library
RADIOACTIVE WASTE DISPOSAL AND MISCELLANEOUS WORK. Annual Report for Calendar Year 1956 (open access)

RADIOACTIVE WASTE DISPOSAL AND MISCELLANEOUS WORK. Annual Report for Calendar Year 1956

None
Date: September 11, 1957
Creator: Seagren, H.E. & Witkowski, E.J. comps.
System: The UNT Digital Library
THE REACTION OF ZIRCONIUM WITH URANIUM DIOXIDE (open access)

THE REACTION OF ZIRCONIUM WITH URANIUM DIOXIDE

An investigation of the causes of observed explosive reaction of zirconium-coated uranium dioxide on dissolution in nitric acid was conducted. It was concluded that such a reaction is to be expected. Possible but unconfirmed methods of alleviating the problem are suggested. (J.R.D.)
Date: June 11, 1957
Creator: Robinson, M.T.
System: The UNT Digital Library
Reactions of Titanium With Water and Aqueous Solutions. Quarterly Report No. 1, (Report No. 2) for March 15-June 15, 1957 (open access)

Reactions of Titanium With Water and Aqueous Solutions. Quarterly Report No. 1, (Report No. 2) for March 15-June 15, 1957

A reactor for investigation of the action of oxygenated water on Ti was constructed, which allows examination of these reactions under any conditions up to 300 deg C and 2000 psi, using either static or dynamic conditions of fiow. Rupture disks made of Ti foil 4 to 12 mils thick reacted violently with O/sub 2/ at any temperature between 30 to 300 deg C, if a fresh surface was exposed by breaking the disks. Such disks did not react with water containing up to 2000 ppm 0/sub 2/, even when a fresh surface was produced. Titanium foil of the same dimensions suspended in the reactor did not react with C2 at temperatures up to 300 deg C, as long as no fresh surface was produced mechanically. (auth)
Date: July 11, 1957
Creator: Littman, F.E. & Church, F.M.
System: The UNT Digital Library
Semi-Annual Summary Research Report in Chemistry for January-June 1957 (open access)

Semi-Annual Summary Research Report in Chemistry for January-June 1957

Heat capacity measurements of yttrium were made from 15 to 350 deg K. Lattice constants are given for rare earth-carbon systems. Thermal analyses were carried out on rare earth fluorides to determine their melting points. The extraction of fission products with silver is discussed. A study was made of the vertical distribution of both Zr and carbon in a sample of U-- Zr alloy prepared from U metal. The degree of immiscibility of U and rare earth metals was determnined, and the results are given. The solubility of Hg in organic solvents at 25 deg C is presented. (W. L.H.)
Date: September 11, 1957
Creator: unknown
System: The UNT Digital Library
Semi-Annual Summary Research Report in Engineering for January-June 1957 (open access)

Semi-Annual Summary Research Report in Engineering for January-June 1957

Progress is reported on: a bastnasite processing procedure; oxidation of Ce)/sup 3+/ in HNO/sub 3/; and liquid metal extraction of fission products from U. (For preceding period see ISC-836.) (T.R.H.)
Date: September 11, 1957
Creator: unknown
System: The UNT Digital Library
SEMI-ANNUAL SUMMARY RESEARCH REPORT IN PHYSICS FOR JANUARY THROUGH JUNE 1957 (open access)

SEMI-ANNUAL SUMMARY RESEARCH REPORT IN PHYSICS FOR JANUARY THROUGH JUNE 1957

Deviations from the allowed spectrum shape observed in P/sup 32/ beta - decay are discussed. Coincidence data taken on Yb/sup 169/ and Tb/sup 160/ are reviewed. The directional correlation function for the 357 to 82 kcv gamma cascade in Cs/sup 133/ following Ba/sup 133/ electron capture decay was determined. The detection of trace oxygen impuritics in metals by the beta activity from x-ray bombardment appears feasible. Results obtained in tests of this mcthod are reported. A pulse heating method for measuring the high- temperature specific heats of metals was developed and applied to Fe in the temperature range 25 to 1000 deg C. The results of electrical resistivity measurements made on Ni and Ni-alloys at temperatures between 25 and 1000 deg C are plotted. Discussions of the semiconducting properties of Mg/sub 2/Si and Mg/ sub 2/Ge single crystals are included. (For preceding period see ISC-833.) (D.E.B.)
Date: September 11, 1957
Creator: unknown
System: The UNT Digital Library
SPECTROGRAPHIC ANALYSIS OF NORMAL HUMAN TISSUE FROM BALTIMORE, MARYLAND (open access)

SPECTROGRAPHIC ANALYSIS OF NORMAL HUMAN TISSUE FROM BALTIMORE, MARYLAND

None
Date: November 11, 1957
Creator: Tipton, I.H.; Cook, M.J.; Steiner, R.L.; Foland, J.M.; McDaniel, K.K. & Fentress, S.D.
System: The UNT Digital Library
Status and Future Requirements for the Uranium-233 Power Reactor Program (open access)

Status and Future Requirements for the Uranium-233 Power Reactor Program

The status of thorium and uraniumn-233 technology for power reactor applications is reviewed. In the areas of fuel cycle, reactor design snd reactor operational problems, information was s developed on current status of techology, current and planned research and developrent programs, need for additional resesrch and developmet, and time schedule of required kilograms of U-23 over the next five years to carry out the research and development now being planned, and the further work believed desirable in the longer term. (auth)
Date: December 11, 1957
Creator: Mash, D. R. & Ottenberg, A.
System: The UNT Digital Library
Ultrasonics for Radioactive Decontamination (open access)

Ultrasonics for Radioactive Decontamination

Tests have been run to determine in a preliminary fashion whether ultrasonic vibration would be effective in removing mixed radioactive deposits from the inside surface of steel pipes in a heat exchanger. Different frequencies (20 KC/S, l000 KC/S) have been used at the maximum power levels conveniently attainable. Different liquids were compared for cleaning effectiveness, with and without ultrasonics. Mild stirring of water bath at room temperature produced virtually no cleaning effect on the samples. Ultrasonics in water, at room temperature, gave 50% to 80% cleaning (as defined by gamma ray count) in 15 minutes or less. Certain chemical solutions gave moderate cleaning results without ultrasonics; but the effectiveness of these solutions was greatly enhanced by the addition of ultrasonics. It was found, as expected, that the effectiveness of the sound wave depended rather critically on the method of coupling to the work. (auth)
Date: November 11, 1957
Creator: Henry, G.E.
System: The UNT Digital Library