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Technical Report Archive and Image Library
1,055
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620
Office of Scientific & Technical Information Technical Reports
504
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248
Texas Attorney General Opinions
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Texas State Publications
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NACA Research Memorandums
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for January 1959
Two alternate systems, acetic acid-nickel and acetic acid-cobalt, were examined for possible replacement of the corrosion system: ferric chloride-nickel which is being used in the current transpiration corrosion protection studies. Two Fluorox fluidized bed runs were made, of 9 and 58 hr duration, in which dry air and oxygen were used as oxidizing and fluidizing gases. Tests of the hydroclone classification of thoria indicated that more than 95% of the +0.5 micron particles can be removed from a sample if 50% recovery of the -0.5 micron particles is acceptable. Fluidized bed denitration of ThNT did not produce large dense ThO/sub 2/ particles, but flame denitration of mixed thorium-uranium- aluminum nitrates produced spherical particles. Three alternate batch Darex flowsheets gave chloride removal to less than 350 ppm with 61% nitric acid feed, while dissolution studies of APPR fuel elements showed that complete dissolution of braze metal in aqua regia may be difficult. Leaching studies of unirradiated UO/sub 2/ pellets showed that the most important variable effecting dissolution rate was the total nitrate content of the dissolvent. Delivery of tae SRE decanning equipment was scheduled for April 1, 1959. Temperatare increases in cylinders of solid radioactive waste were calculated for APPR fuel …
Date:
April 30, 1959
Creator:
Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Object Type:
Report
System:
The UNT Digital Library
CUREBO: A GENERALIZED TWO-SPACE-DIMENSIONAL CODING WITH CROSS-SECTION AND DEPLETION CALCULATIONS FOR THE IBM 704
The CUREBO code for the IBM 704 is described. The code is divided into three parts including the calculation of nuclear cross section of the various physical components of a reactor (WOX7), the solution of the multigroup diffusion equations in two-space dimensions in order to find neutron fluxes and sources for an operating reactor containing these components ( CURE), and the calculation of fuel and poison depletion as a result of operating this reactor under steady- state conditions (BO2). (auth)
Date:
April 30, 1959
Creator:
Archibald, J.A. Jr.
Object Type:
Report
System:
The UNT Digital Library
Description of Purex Plant Process
A brief summary, with reference literature for details, of pertinent and important process flowsheet conditions which are in use in the Purex Process is presented. (auth)
Date:
April 30, 1959
Creator:
Irish, E. R.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout. Summary Report
Preliminary studies were made of the relationship between the size of particles suspended in the lower atmosphere and the amount and nature of radionuclides they contain. Emphasis was placed on the distribution of strontium90. From a limited number of analyses, it was found that strontium-90 is associated primarily with particles below 0.1 micron in diameter. Preliminary studies were made of scavenging of particles by liquid water droplets. Studies are included of sticking probability and the effects of Brownian motion and water vapor diffusion. It was found that electrostatic effects are of primary importance for 1.9-micron (mean volume diameter) particles. Brownian motion and water vapor diffusion did not contribute to the scavenging. These results are based on known and new equations derived for various scavenging conditions. (auth)
Date:
April 30, 1959
Creator:
Rosinski, J. & Stockham, J.
Object Type:
Report
System:
The UNT Digital Library
Preliminary Studies of Scavenging Systems Related to Radioactive Fallout : Summary Report, April 1, 1958 to March 31, 1959
This report is the final in a series of preliminary reports that follow the studies of scavenging systems related to radioactive fallout. The project consisted of two phases: preliminary experiments to relate the sizes of particles in air to specific radioisotopes, and preliminary laboratory studies of scavenging of particles by liquid drops, including studies of sticking probability and effects of Brownian motion and water vapor diffusion.
Date:
April 30, 1959
Creator:
Rosinski, John & Stockham, John D.
Object Type:
Report
System:
The UNT Digital Library
Production Test IP-261-C determination of power rate meter response
This test will determine approximately the relationship between the power rate of rise indicated by the power rate meter and the actual pile power, rising period, and power rate. The actual pile power and power rate cannot be measured accurately during rapidly changing conditions; it is the intent of this test primarily to demonstrate that rate of rise protection offered by the power rate meter an be calculated to the same order of accuracy as the measurements of actual conditions.
Date:
April 30, 1959
Creator:
Simpson, D. E.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Report of the Solution Materials Section for the Period Ending April 30, 1959
Studies concerned with the deposition of salts from simulated fuel solution under boiling conditions were continued. Additional deposition tests were carried out in loop L-2-23 in which the core section was heated. Several reagents were tested to determine their ability to dissolve stainless steel corrosion products. A simulated HRT fuel solution was stable with regard to U concentration when diluted to 23 ppm at 250 C; however, some Cu was lost from solution. Preliminary tests in a uranyl sulfate solution indicate that an 18-8 stainless steel alloyed with either small amounts of Pt or Cu is more corrosion resistant at low flow rates than a conventional 18-8 stainless steel; however, the addition of either Cu or Pt did not reduce the corrosion rate of 18stainless steel at high flow rates. A study was made to determine the susceptibility of off-specification type 347 stainless steel to intergranular attack by uranyl sulfate solutions. Continued testing with a single heat of cast type 347 stainless steel has confirmed previously reported data to the effect that the cast alloy is more resistant a stress-corrosion cracking than is the wrought alloy. Six commercial grades of Al/sub 2/O/sub 3/ suitable for use as check balls in …
Date:
April 30, 1959
Creator:
Griess, J. C.; Savage, H. C.; Greeley, R. S.; English, J. L.; Bolt, S. E.; Hess, D. N. et al.
Object Type:
Report
System:
The UNT Digital Library
Results of reverse flow experimental tests for C operational charge-discharge tube at low tub powers
The purpose of this report is to present the results of laboratory experiments in which coolant water flowed backwards through a ``C`` reactor process tube with operational charge-discharge front fittings under conditions of typical reactor rear header pressures and post-scram rear header water temperature and tube powers. This information is of value in planning and interpreting transient experiments investigating the consequences of the rupture of reactor front face piping to a single tube.
Date:
April 30, 1959
Creator:
Fitzsimmons, D. E. & Hesson, G. M.
Object Type:
Report
System:
The UNT Digital Library
Studies of Zirconium-Iron-Tin Alloys. Report No. 6 (Final) for July 1, 1958-March 31, 1959
The intermetallic compounds of the zirconium-irontin system (i.e., ZrFe/ sub 2/ and Zr/sub 4/Sn) were studied at 500 and 1100 C. The alloys were prepared from iodide zirconium and high-purity iron and tin by nonconsumableelectrode arc melting techniques under an inert atmospherc. Specimens were encapsulated in Vycor and annealed at the prescribed temperatures followed by a water quench. Data were gathered through the use of metallographic, x-ray diffraction, visible incipient melting, and magnetic susceptibility techniques. It was determined that Zr/sub 4/Sn (24.5 wt.% Sn) and (24.5 wt.% Sn and 7 to 8 wt.% Fe) are separate phases which are not in equilibrium with each other. ZrFe/sub 2/ was firmly established at its stoichiometric composition of 55 wt.% Fe, and it apparently has negligible solubility for tin. The specific magnetization of this ferromagnetic compound is of thc order of 55 cgs at room temperature. Its Curie temperature is about 355 C. (auth)
Date:
April 30, 1959
Creator:
Tanner, L.E. & Simcoe, C.R.
Object Type:
Report
System:
The UNT Digital Library
Design of production test IP-247-A-8-FP, irradiation of 1.47% enriched self-supported I & E fuel elements in ribless process tubes
None
Date:
April 29, 1959
Creator:
Hodgson, W. H. & Hall, R. E.
Object Type:
Report
System:
The UNT Digital Library
Effects From the Tail of Simulated Nuclear Weapon Thermal Pulses
None
Date:
April 29, 1959
Creator:
Barner, H. & Hinshaw, J. R.
Object Type:
Report
System:
The UNT Digital Library
Filling Instructions for the Pratt & Whitney Forced Convection Liquid Metal Inpile Loop Experiment (PW19)
The apparatus and procedures that are to be used to fill the liquid metal system of the Pratt and Whitney Forced Convection Liquid Metal Inpile Loop are described. The liquid metal to be used is a mixture containing 56% Na and 44% K, which is a liquid at room temperature. In order to simplify the filling procedure at the reactor site, two containers, each of which contains exactly enough liquid metal to fill the experiment to the prescribed level, a fill dolly incorporating a purified helium system, and an evacuation system will be provided at the reactor site. After completion of the liquid metal transfer, the liquid metal fill tube will be crimped, cut, and seal welded. The liquid metal and helium systems will then be pressurized through the helium fill tubes, which will also be crimped, cut, and seal welded. Each tube seal weld will be inspected after completion of the weld by mass spectrometry leak check and dye penetrant fault detection
Date:
April 29, 1959
Creator:
Heyl, P. T.
Object Type:
Report
System:
The UNT Digital Library
New Concepts for Control and Use of Nuclear Explosions
None
Date:
April 29, 1959
Creator:
Porzel, F. B.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Health Physics Through March 31, 1959
None
Date:
April 29, 1959
Creator:
Meyer, H.E.
Object Type:
Report
System:
The UNT Digital Library
Shear Strength of Simply Supported Prestressed Concrete Beams Having Web Reinforcement
Abstract: Tests were made on 24 simply supported, post-tensioned, end-anchored, prestressed concrete beams with and without web reinforcement.
Date:
April 29, 1959
Creator:
Holt, Randolph E.
Object Type:
Report
System:
The UNT Digital Library
Texas Attorney General Opinion: WW-610
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: Is the Commissioners' Court compelled to pay $2,900.00, or can the Court excise discretion and pay nothing, or any amount not to exceed $2,900.00, under Section 2A of Senate Bill 78, Acts of the 52nd Legislature, Regular Session, 1951, Chapter 303, Page 485 (Codified as Article 6819a-3, Vernon's Civil Statutes.)
Date:
April 29, 1959
Creator:
Texas. Attorney-General's Office.
Object Type:
Text
System:
The Portal to Texas History
TRANSURANIC STUDIES STATUS AND PROBLEM STATEMENT
The purpose of the Transuranics Program is to develop separation processes for the transuranic elements, primarily those produced by long-term neutron irradiation of Pu/sup 239/. The program includes laboratory process development, pilot-plant process testing, processing of 10 kg of Pu/sup 239/ irradiated to greater than 99% burn-up for plutonium and americium-curium recovery, and processing the reirradiated plutonium and americium-curium fractions. The proposed method for processing highly irradiated plutonium is: (1) plutonium-aluminum alloy dissolution in HNO/sub 3/; (2) plutonium recovery by TBP extraction; (3) americium, curium, and rare-earth extraction by TBP from neutral nitrate solution; (4) partial rare-earth removal (primarily lanthanum) by americium-curium extraction into 100% TBP from 15M HNO/sub 3/; (5) additional rare-earth removal by extraction in 0.48M mono-2-ethylhexylphosphoric acid from 12M HCl; and (6) americium-curium purification by chloride anion exchange. Processing through the 100% TBP, 15M HNO/sub 3/ cycle can be carried out in the Power Reactor Fuel Reprocessing Pilot Plant. New facilities are proposed 15M HNO/ sub 3/ cycle can be carried out in the Power Reactor Fuel Reprocessing Pilot Plant. New facilities are proposed for laboratory process development studies and the final processing of the transplutonic elements. (auth)
Date:
April 29, 1959
Creator:
Leuze, R E
Object Type:
Report
System:
The UNT Digital Library
Properties of Uranium Dioxide-Stainless Steel Dispersion Fuel Plates
The physical and mechanical properties of GCRE-type fuel elements were determined from room temperature to 1650 deg F. The fuel elements were prepared by cladding Type 318 stainless steel sheet to a core containing 15 to 35 wt.% UO/ sub 2/ in either prealloyed Type 318 stainless steel or elemental iron-18 wt.% chromium-14 wt. % nickel-2.5 wt. % molybdenum. The tensile strength in the direction perpendicular to the rolling plane decreased from 24,600 psi at room temperature to 9,200 psi at 1650 deg F for the reference fuel plate, whose core contained 25 wt.% UO/sub 2/ in the elemental alloy. The tensile strength in the longitudinal direction for this fuel element ranged from 54,800 psi at room temperature to 14,200 psi at 1650 deg F, with elongation in 2 in. ranging from 8 to 13 per cent. The extrapolated stress for 1000hr rupture life at 1650 deg F was 1800 psi, and a 1.4T bend was withstood without cracking. The mean linear thermal coefficient of expansion was 11.0 x 10/sup -6/ per deg F for the range 68 to 1700 deg F. (auth)
Date:
April 28, 1959
Creator:
Paprocki, S. J.; Keller, D. L. & Fackelmann, J. M.
Object Type:
Report
System:
The UNT Digital Library
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
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
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
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
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
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