Resource Type

States

The Economics of Nuclear Power (open access)

The Economics of Nuclear Power

Economic aspects of nuclear power development in the U. S. are tabulated and graphed. Included are figures on presently operating reactors as well as those contemplated or scheduled. Also a brief description of the objectives of short- and long-range programs is given as well as tables listing some of the characteristics of each reactor. (J.R.D.)
Date: April 27, 1959
Creator: Lane, J.A.
Object Type: Report
System: The UNT Digital Library
THE EFFECT OF IMPURITIES ON IRON-CHROMIUM-YTTRIUM ALLOYS (open access)

THE EFFECT OF IMPURITIES ON IRON-CHROMIUM-YTTRIUM ALLOYS

A study was made of the effect of carbon, manganese, oxygen, palladium, and sulfur on the structure and fabricability of iron-35 wt.% chronium-1 wt.% yttrium alloy. Using a vacuum-induction melting technique each of the additives except oxygen was introduced to 1-lb remelts of a single 15-lb master alloy. The master alloy and remelts were made under similar melting, pouring, and casting conditions. Oxygen was introduced as Fe/sub 2/0/sub 2/ by inertelectrode arc melting to avoid extraneous, uncontrolled contamination stemming from crucible contact. Photomicrographs were prepared of as-cast metal illustrating structural variations. Ingots obtained were fabricated to 0.050-in. sheet at 2000 deg F to compare fabrication characteristics with those of the control ingot containing no additives. As a qualitative measure of metal soundness and ductility, a portion of each of the 0.050-in. sheets was further reduced at room temperatare to 3-mil foil. During melting at 2900 to 3000 deg F under controlled conditions, the amount of yttrium present in the charge was reduced roughly 50% by reaction with the alumina crucible. Sulfide, added as FeS, and oxide additions also lowered the amount of yttrium retained in ingots. The maximum amount of sulfur retained in an alloy of nominal composition iron-35 wt.% …
Date: April 27, 1959
Creator: Endebrock, Row W.; Chubb, Walston; Foster, Ellis L. & Dickerson, Ronald F.
Object Type: Report
System: The UNT Digital Library
FLOODING CHARACTERISTICS OF 1/4-in. FLUOROTHENE RASCHIG RINGS (open access)

FLOODING CHARACTERISTICS OF 1/4-in. FLUOROTHENE RASCHIG RINGS

The flooding characteristics of fluorothene Raschig rings at low liquid rates with the existing literature data on carbon rings are compared. Visual observations of flooding in the air-water system were correlated with pressure drop using a 3-in. i.d. glass column having an 18-in. long fluorothene Raschig ring packed section. A comparison of extrapolated literature data with these experimental data indicates thc gas flow rates required to flood fluorothene packing are slightly higher than for carbon packing. At a liquid flow rate of 537 lbs/hr-ft/sup 2/, fluorothene rings flooded at a gas velocity of 842 lbs/hr- ft/sup 2/ whereas carbon rings are reported to fiood at a gas velocity of approximately 755
Date: April 27, 1959
Creator: Boles, R. L. & Stainker, S. H.
Object Type: Report
System: The UNT Digital Library
Heat Transfer Study for Self-Boiling Radioactive Wastes (open access)

Heat Transfer Study for Self-Boiling Radioactive Wastes

The temperature characteristics associated with the handling of self-boiling radioactive wastes from the separations extraction processes in the Chemical Processing Department have necessitated several heat transfer studies. Earlier studies 1,2,3 defined the feasibility of self-concentration in existing waste storage facilities by determining the rate of heat generation from the decay of stored fission products and by defining the rate of heat loss from existing storage tanks to the surrounding soil.
Date: April 27, 1959
Creator: Stivers, H.W. & Taylor, H.W.
Object Type: Report
System: The UNT Digital Library
Niobium Phase Diagrams : Manuscript Report on Niobium-Oxygen System (open access)

Niobium Phase Diagrams : Manuscript Report on Niobium-Oxygen System

Abstract: "The niobium-oxygen equilibrium has been determined by metallographic examination of arc-cast alloys made of electron-gun-refined niobium metal and special purity niobium pentoxide. Two intermediate oxides, NbO and NbO2, melt without decomposition at 1945 C and 1915 C, respectively. Eutectic reactions exist between niobium and NbO and 1915 C and between NbO and NbO2 at 1810 C. Experimental supports a peritectic reaction between NbO2 and Nb2O5 1510 C. The maximum solid solubility of oxygen in niobium metal is 0.72 weight per cent."
Date: April 27, 1959
Creator: Elliott, Rodney P.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: WW-605 (open access)

Texas Attorney General Opinion: WW-605

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: Applicability of statutes of limitation to the cause of action involved in House Concurrent Resolution 55 of the 56th Legislature, and related questions.
Date: April 27, 1959
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
The Effects of Ternary Alloying Additions on the Corrosion Resistance of Epsilon-Phase Uranium-Zirconium Alloys (open access)

The Effects of Ternary Alloying Additions on the Corrosion Resistance of Epsilon-Phase Uranium-Zirconium Alloys

Abstract: "The corrosion rate in 680 F water of the uranium-50 w/o zirconium binary alloy was found to be -0.20 mg/(cm2)(hr), and that of the uranium-40 w/o zirconium binary alloy was -0.34 mg/(cm2)(hr). Both alloys correlated uniformly, with no evidence of discontinuous failure. Normal variations in interstitial content in either alloy had no significant effect on corrosion behavior. Tantalum additions, in the range of 0.2 to 5 w/o, improved the corrosion rate of the uranium-50 w/o zirconium base, with a minimum rate of -0.06 mg/(cm2)(hr) for the 5 w/o tantalum alloy. The 5 w/o tantalum addition to the uranium-40 w/o zirconium alloy. The 5 w/o tantalum addition to the uranium-40 w/o zirconium alloy decreased the corrosion rate of the base to -0.11 mg/(cm2)(hr) in the [...] condition only. In either conditions, the 5 w/o tantalum alloy failed discontinuously. All other additions to both bases either had no effect or decreased corrosion resistance. These included aluminum, chromium, iron, molybdenum, nickel, platinum, tin, titanium, tungsten, and vanadium additions."
Date: April 27, 1956
Creator: Reynolds, James E.; Berry, Warren E., 1922-; Ogden, Horace R.; Peoples, Robert S. & Jaffee, Robert Isaac, 1917-
Object Type: Report
System: The UNT Digital Library
THE EFFECTS OF TERNARY ALLOYING ADDITIONS ON THE CORROSION RESISTANCE OF EPSILON-PHASE URANIUM-ZIRCONIUM ALLOYS (open access)

THE EFFECTS OF TERNARY ALLOYING ADDITIONS ON THE CORROSION RESISTANCE OF EPSILON-PHASE URANIUM-ZIRCONIUM ALLOYS

None
Date: April 27, 1956
Creator: Reynolds, James E.; Berry, Warren E.; Ogden, Horace R.; Peoples, Robert S. & Jaffee, Robert I.
Object Type: Report
System: The UNT Digital Library
Notes on Sheath meeting at SRI, April 17-18, 1956 (open access)

Notes on Sheath meeting at SRI, April 17-18, 1956

Dr. Laurence opened the discussion by saying that AECL is concentrating its interest on fuel rods for NRU to be ready at the end of the year; these will be unbonded, based on NRX experience. Chalk River, however, is prepared to go to bonded fuel elements,and how has in extrusion cladding at AlCan an alternate process. AECL is putting its trust in extrusion clad flat plates for the immediate future. General Electric Co. of Canada is now making UO{sub 2} fuel rods; these are UO{sub 2} pellets machined and threaded into a sheath. They are hoped to be useful for higher temperature operation.
Date: April 27, 1956
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Pile Periods and the Inhour Equation Accounting for Delayed Neutron Groups from Fission of U²³⁵ and Pu²³⁹ (open access)

Pile Periods and the Inhour Equation Accounting for Delayed Neutron Groups from Fission of U²³⁵ and Pu²³⁹

Calculations are presented regarding the effect of delayed neutrons in reactors fueled with mixtures of Pu²³⁹ and U²³⁵. Results are plotted to illustrate the change in thermal flux as a function of time for various positive or negative step changes in reactivity.
Date: April 27, 1956
Creator: Astley, E. R.
Object Type: Report
System: The UNT Digital Library
PROCEDURE FOR CLEANING THE LOW AND HIGH-PRESSURE FUEL AND BLANKET SYSTEMS WITH TRISODIUM PHOSPHATE HRT ENGINEERING TEST PROCEDURE (open access)

PROCEDURE FOR CLEANING THE LOW AND HIGH-PRESSURE FUEL AND BLANKET SYSTEMS WITH TRISODIUM PHOSPHATE HRT ENGINEERING TEST PROCEDURE

None
Date: April 27, 1956
Creator: Search, H.K.
Object Type: Report
System: The UNT Digital Library
Carbon Steel Program for High Temperature Reactor Systems (open access)

Carbon Steel Program for High Temperature Reactor Systems

The Reactor Design and Development Unit has just completed a design concept for an intermediate capacity dual purpose reactor plant utilizing carbon steel for the primary loop portion outside the reactor. This design concept is reported in HW-33157 AD (2). The economic and engineering gains are of sufficient magnitude to justify an accelerated and extensive test program to completely evaluate the remaining unknowns in utilizing carbon steel as a stainless steel substitute. It is the purpose of this document to up-date and elaborate the information contained in the two previous documents (1). . It is the further purpose to define the program required to implement the design concept developed by the Reactor Design and Development Unit (2) utilizing carbon steel as the primary loop structural material.
Date: April 27, 1955
Creator: Pearl, W. L.
Object Type: Report
System: The UNT Digital Library
THE MEASUREMENT OF DYNAMIC PRESSURE DROP IN A PULSE COLUMN. Progress Report No. 12 on THE PERFORMANCE OF CONTACTORS FOR LIQUID-LIQUID EXTRACTION (open access)

THE MEASUREMENT OF DYNAMIC PRESSURE DROP IN A PULSE COLUMN. Progress Report No. 12 on THE PERFORMANCE OF CONTACTORS FOR LIQUID-LIQUID EXTRACTION

None
Date: April 27, 1955
Creator: Erickson, E.E.; Knight, R.M. & Pike, F.P.
Object Type: Report
System: The UNT Digital Library
Potential Nitrate Decomposition High Level Waste Storage (open access)

Potential Nitrate Decomposition High Level Waste Storage

It is recommended that self-concentration of Purex wastes should not be started until much more complete knowledge is obtained of the conditions and reactions in these wastes. The presently planned tests in the Semi-Works will be a practical demonstration of the problems but will be of little value on the initial Purex wastes as these tests are being run almost concurrent with the filling of the first Purex storage tank.
Date: April 27, 1955
Creator: Anderson, C. R.
Object Type: Report
System: The UNT Digital Library
Measurements of Normal-Force-Coefficient Fluctuation on Four 9-Percent-Thick Airfoils Having Different Locations of Maximum Thickness (open access)

Measurements of Normal-Force-Coefficient Fluctuation on Four 9-Percent-Thick Airfoils Having Different Locations of Maximum Thickness

Memorandum presenting a two-dimensional wind-tunnel investigation of the effects of maximum-thickness location on fluctuating pressures and normal-force coefficients on 9-percent-thick airfoils, which indicated that for normal-force coefficients up to 0.6, the section variables had little effect on the pressure pulsations and root-mean-square normal-force-coefficient fluctuations. Results regarding pressure fluctuations and normal-force-coefficient fluctuations are provided.
Date: April 27, 1954
Creator: Humphreys, Milton D.
Object Type: Report
System: The UNT Digital Library
Maximum capacities of the 100-B water plant (open access)

Maximum capacities of the 100-B water plant

Increases in process water flows will be needed as the current program of increasing pile power levels continues. The future process water flows that will be required are known to be beyond the present maximum capacities of component parts of the water system. It is desirable to determine the present maximum capacities of each major component part so that plans can be mode for modifications and/or additions to the present equipment to meet future required flows. The apparent hydraulic limit of the present piles is about 68,000 gpm. This figure is based on a tube inlet pressure of 400 psi, a tube flow of 34 gpm, and 2,000 effective tubes. In this document the results of tests and calculations to determine the present maximum capacities of each major component part of the 100-B water system will be presented. Emergency steam operated pumps will not be considered as it is doubtful of year around operation of a steam driven pump could be economically justified. Some possible ways to increase the process water flows of each component part of the water system to the ultimate of 68,000 gpm are given.
Date: April 27, 1953
Creator: Strand, N. O.
Object Type: Report
System: The UNT Digital Library
MTA Quarterly Progress Report - December, 1952, January, February, 1953 (open access)

MTA Quarterly Progress Report - December, 1952, January, February, 1953

Progress reports on Accelerator Development Program, High Frequency Program, beam dynamics in strong focusing linear accelerators, spiral beam buncher experiments, dynamical properties of Mark I, mechanical design, and Target Physics Program.
Date: April 27, 1953
Creator: University of California Radiation Laboratory
Object Type: Report
System: The UNT Digital Library
Preliminary Study of a Uranium - Bismuth Liquid Fuel Power Reactor L. F. R . 2 (open access)

Preliminary Study of a Uranium - Bismuth Liquid Fuel Power Reactor L. F. R . 2

Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.
Date: April 27, 1951
Creator: Gurinsky, D. H.; Kaplan, I.; Miles, F. T.; Williams, C. & Winsche, W. E.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: V-1172 (open access)

Texas Attorney General Opinion: V-1172

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, Price Daniel, regarding a legal question submitted for clarification: Legality of the Board's paying architectural fees prior to the execution of construction contracts; necessity of approval of architectural contracts by the Board of Control.
Date: April 27, 1951
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Rough-Water Tests of Models of the Vosper and Plum Planing Boats (open access)

Rough-Water Tests of Models of the Vosper and Plum Planing Boats

Models of two types of high-speed surface craft were tested in Langley tank no. 1 to obtain rough-water data for an evaluation by the David Taylor .Model Basin of the relative merits of the designs. Time-history records were obtained of trim, rise, and normal acceleration at two points in the hulls for various speeds and two sizes of waves.
Date: April 27, 1950
Creator: Chambliss, Derrill B. & Blanchard, Ulysse J.
Object Type: Report
System: The UNT Digital Library
Texas Attorney General Opinion: V-1047 (open access)

Texas Attorney General Opinion: V-1047

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, Price Daniel, regarding a legal question submitted for clarification: The eligibility for a chiropractic license of one previously convicted of a felony.
Date: April 27, 1950
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Theoretical Investigation of the Dynamic Lateral Stability Characteristics of the Douglas X-3 Research Airplane, Study 41-B (open access)

Theoretical Investigation of the Dynamic Lateral Stability Characteristics of the Douglas X-3 Research Airplane, Study 41-B

Report presenting calculations of the dynamic lateral stability characteristics of a mock-up configuration of the Douglas X-3. The oscillations were found to be stable for all calculations investigated but would not meet the Air Force damping requirements for the majority of the conditions. The use of an autopilot was found to greatly improve oscillation damping.
Date: April 27, 1950
Creator: Bennett, Charles V.
Object Type: Report
System: The UNT Digital Library