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EXPERIMENTAL MEASUREMENTS OF THE SUCTION HEAD REQUIRED BY THE HALLAM PROTOTYPE FREE SURFACE SODIUM PUMP
Hydraulic tests were made on the Hallam Prototype Free-Surface Sodium Pump to determine the net positive suction head (NPSH) required at various sodium flow rates. Pump performance data were also collected. The results indicate that an NPSH of 22 ft sodium is required at the design flow rate of 7200 gpm at approximates 1000 deg F, agreeing with computed values, and that the pump is designed with a safety margin of slightly over l0%. (D.L.C.)
Date:
July 25, 1961
Creator:
Atz, R.W.
Object Type:
Report
System:
The UNT Digital Library
CHEMICAL TECHNOLOGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961
Activities in research programs are summarized in the areas of power reactor fuel processing, fluoride volatility processing, molten salt reactor fuel processing, homogeneous reactor fuel processing, waste treatment and disposal pilot plant decontamination, GCR coolant purification studies, equipment decontamination, HRP thoria blanket development, fuel cycle development, transuranium element studies, production of U/sup 232/, uranium processing, fission product recovery, thorium recovery from granite, solvent extraction technology, mechanisms of separation processes, radiation effects on catalysts, ion exchange technology, chemical engineering research, chemical applications of nuclear explosions, reactor evaluation studies, and assistance programs. (J.R.D.)
Date:
September 21, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
CASTING OF LONG AND THIN PLATES OF URANIUM-MOLYBDENUM ALLOYS
The development of procedures for the vacuum induction casting of U--Mo alloys into both thin (0.010 to 0.100-in. thick) plates and long (36 in.) plates is described. Melting and casting cycles were developed, and casting techniques established, which resulted in sound, integral plates. These plates were evaluated by radiographic and metallographic examination, and by chemical analysis. The results indicated the feasibility of the process for the fabrication of fuel plates for nuclear reactors. The process promises a potential reduction in fabrication costs, by eliminating waste. (auth)
Date:
November 1, 1961
Creator:
Katz, N.H. & Binstock, M.H.
Object Type:
Report
System:
The UNT Digital Library
Analytical Chemistry of the Polyphosphates
Additional data were obtained on the separation of linear polymers from cyclic polymers by precipitation with barium chloride. An unexpected peak was observed in the anion-exchange chromatography of a sodium poly-phosphate of n-bar average degree of polymerization) = 6, and the compound represented by this peak was isolated. An end-group titration of this compound by microtechnique proved unequivocally that it is a cyclic phosphate. Although the identification (number of phosphorus atoms per molecule) is not completed, evidence from its position in the elution graph by ion-exchange chromatography' and from paper chromatography indicate that it is probable pentametaphosphate, Na/sub 5/P/sub 5/O/sub 15/, or the boat form of tetrametaphosphate, Na/sub 4/P/sub 4/O/sub 12/. (P.C.H.)
Date:
October 17, 1961
Creator:
Rieman, W., III & Rothbart, H. L.
Object Type:
Report
System:
The UNT Digital Library
Use Test Comparison of TBP Diluents
Several diluents for possible use in TBP Purex Plant solvent were tested. The tests included nitric --nitrous acid degradation, fission prcduct distribution under simulated plant conditions, emulsillcation, and radiolysis. The order of quality of four diluents is n-dcdecane> Soltrol 170> Shell Code 85030(82000)> Shell E-2342. (D.L.C.)
Date:
July 1, 1961
Creator:
Mendel, J. E.
Object Type:
Report
System:
The UNT Digital Library
SOLID STATE DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING AUGUST 31, 1961
Progress in solid state physics is reported on the following topics: theory, metals and alloys, nonmetals, reactor materials, and special projects. Twenty-one separate abstracts were prepared. (M.C.G.)
Date:
December 29, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
The Thermodynamic Properties of the Alkali Halides
The thermodynamic properties of the alkali halides are reviewed, presenting data supplementary to that of Brewer and Brackett, Chem. Rev. 61: 425-432(1961). (T.R.H.)
Date:
November 1961
Creator:
Brewer, L.
Object Type:
Report
System:
The UNT Digital Library
LITHIUM HYDRIDE PROPERTIES
A tabulation is presented of values for selected properties of lithium hydride. (M.C.G.)
Date:
March 14, 1961
Creator:
Welch, F.H.
Object Type:
Report
System:
The UNT Digital Library
SEPARATION OF TRANSPLUTONIUMS FROM LANTHANIDES BY TERTIARY AMINE EXTRACTION
None
Date:
December 20, 1961
Creator:
Baybarz, R.D. & Weaver, B.
Object Type:
Report
System:
The UNT Digital Library
Noise Considerations in Nuclear Pulse Amplifiers
The effects of certain pulse-shaping networks on the signal-to-noise ratio of a nuclear pulse amplifier were considered. The shaping networks discussed are: equal RC-integrating and RC-differentiating time constant, single- delay-line clipper and RC integrator, and doubledelay-line clipper and RC integrator. The effects of these networks on the signal, when high count rates and overload pulses are present, were also considered. Equations and curves were developed for the energy resolution (signal-tonoise ratio) and resolving time (related to the ability to operate at high counting rates) of the networks. Experimental results are shown for the energy resolution of the types of pulse- shaping networks considered. (auth)
Date:
December 20, 1961
Creator:
Landis, D. A.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
Doppler Broadening of the Low Energy Total Neutron Cross Section of Pu-241
None
Date:
August 1, 1961
Creator:
Simpson, O. D. & Marshall, N. H.
Object Type:
Report
System:
The UNT Digital Library
Reactor Development Program Progress Report (for) July 1961
A summary is presented of activities in reactor and general engineering research programs. Discussions are included for developments in EBWR, BORAX-V, ZPR-III. ZPR-VI, ZPR-IX, EBR-I, and EBR-II. Reactor safety studies were performed for fast and thermal reactors. Nuclear technology developments are discussed for applied nuclear and reactor physics, reactor fuels and materials development, heat engineering studies, separations processes, and advanced reactor concepts. (B.O.G.)
Date:
August 15, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Congressional Priviledge: Immunity from Liability for slander and Libel
This report is about the congressional priviledge, because of which people could be immune to liabilities for Slander and Libel.
Date:
February 24, 1961
Creator:
Sharp, Freeman W.
Object Type:
Report
System:
The UNT Digital Library
STRUCTURES OF THE INTERMEDIATE PHASES Ni$sub 10$Zr$sub 7$ AND Ni$sub 10$Hf$sub 7$
None
Date:
February 1, 1961
Creator:
Kirkpatrick, M. E.; Smith, J. F. & Larsen, W. L.
Object Type:
Report
System:
The UNT Digital Library
Material Buckling Measurements on Graphite-Uranium Systems at Hanford: A Summary Tabulation
Measurements of material bucklings for graphite uranium systems are summarized. A comprehensive listing and guide to the original data sources is provided. Complete information on physical and nuclear properties of the lattice and the geometry of the exponential assembly is included, along with some of the auxiliary data taken. The fuel sizes vary from 0.925 to 2.5 in. in diameter for five different fuel geometries. The lattice spacings vary from 4 3/16 to 15 in. Over 300 measurements of material buckling are included. (auth)
Date:
May 1, 1961
Creator:
Wood, D. E.
Object Type:
Report
System:
The UNT Digital Library
Remote Plastic Bag Passout Unit for High-Level Radiochemical Operations
A system is designed for making remote sealed-bag passouts from a multicurie-level chemistry processing enclosure. The polyethylene bags are changed remotely without exposing contaminated surfaces while always maintaining a low leak rate seal. The system employs an interchange box (passout box) attached to the chemistry enclosure. Integrated with the box is a hydraulically operated jack that raises and lowers the bags, and a welder-cutter for sealing them. A single master-slave manipulator teamed with the above units handles all operations. (auth)
Date:
August 1, 1961
Creator:
Fleischer, E. S.; Parsons, T. C. & Howe, P. W.
Object Type:
Report
System:
The UNT Digital Library
EXTRACTION OF NEPTUNIUM FROM ACIDIC SOLUTIONS BY ORGANIC NITROGEN AND PHOSPHORUS COMPOUNDS
Neptunium distribution coefficients from acid nitrate, chloride, and sulfate solutions by several organic nitiogen and phosphorus compounds were measured as functions of several extraction variables, including neptunium valence, acid and salt concentration, and reagent concentration. Extractability by all the reagents varied in the order Np(IV)> Np(VI)>> Np(V). Except for primary amines, all reagents extracted Np(IV) much more strongly from nitrate than sulfate solutions. Among organonitrogen compounds the order of extractability of Np(IV) was: quaternary> tertiary> primary and secondary from nitrate solutions but primary>> secondary> tertiary from sulfate solutions. Neptunium(IV) nitrate extractions with the different extractants passed through maxima at widely different acid concentrations. In most cases, extraction increased when nitric acid was replaced by nitrate salt. Extraction was usually approximately proportional to the square of the reagent concentration. (auth)
Date:
October 19, 1961
Creator:
Weaver, B.
Object Type:
Report
System:
The UNT Digital Library
Hazards Report for the BF3 Withdrawal Mechanism in the SM-1
A design and operational description is presented of a BF/sub 3/ withdrawal mechanism planned for installation on one of the two startup channels at the SM-1. An analysis of possible malfunctions is included. (J.R.D.)
Date:
October 13, 1961
Creator:
Coombe, J. R.
Object Type:
Report
System:
The UNT Digital Library
RADIOISOTOPE AND RADIATION APPLICATIONS QUARTERLY PROGRESS REPORT. SECTION I. USE OF INTRINSIC RADIOACTIVE TRACERS FOR PROCESS CONTROL. SECTION II. RADIATION-INDUCED GRAFT-POLYMERIZATION STUDIES
Research was continued in the areas of intrinsic radioactive tracers for industrial process control and the influence of structural factors in radiation- induced graft polymerization. The use of in-process isotope neutron soarces to produce short-lived radiotraces is discussed. A 10c Po--Be neutron source was obtained for exploratory experiments. The design and construction of a neutronsource storage shield and an activatioa-cell holder are underway. The effect of structural factors oii the eIficiency of free-radical site formation in acrylate and methacrylate polymers was emphasized. Site measurements versus dose were made for poly-n-hexylmethacrylate. Two additional methods for measuring free-radical conceiitrations, a chemical method employing diphenylpicrylhydrazyl and hydroquinone and a method based on molecular-weight decreases, were developed. The grafting studies were continued. (M.C.G.)
Date:
October 23, 1961
Creator:
McFarling, J.L.; Gluck, P.; Kircher, J.F.; Sunderman, D.N.; Sliemers, F.A.; Luttinger, M. et al.
Object Type:
Report
System:
The UNT Digital Library
Dimensional Behavior of the Experimental Gas-Cooled Reactor Fuel Element at Elevated Temperatures
The Experimental Gas-Cooled Reactor (EGCR) fuel assemblies consist of a cluster of seven fuel elements contained in a graphite sleeve. Each element is composed of hollow cylindrical UO/sub 2/ pellets encapsulated in a type 304 stainless steel tube. The dimensional behavior of the fuel element was determined in an apparatus which simulated the thermal conditions predicted for the EGCR. Particular emphasis was placed on determining the relationship between the fuel temperature and axial expansion, the radial expansion characteristics of the fuel, the effect of cladding and fuel interaction on heating and subsequent cooling, the effect of rapid temperature excursions on the degradation of the fuel, and accumulative effects in the fuel element due to thermal cycling. An element that contains a radial gap between the cladding and the fuel pellet was found to respond to thermal cycling in the same manner that the individual components would react if subjected to the same thermal conditions and tested separately. Both the axial and radial expansion of the fuel pellet are very nearly a function of the maximum central temperature. The axial expansion of the fuel pellet column can be reduced appreciably at elevated temperatures by "dishing" the ends of the pellets. The …
Date:
August 1, 1961
Creator:
Martin, W. R. & Weir, J. R.
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF PLUTONIUM BEARING FUEL MATERIALS. Progress Report for Period April 1 through June 30, 1961
BS>Activities are discussed for work done in the preparation of PuO/sub 2/ using the continuous oxalate process, and continuous coprecipitation studies using a uranium-20 wt% plutonium nitrate feed solution. Characterization studies of the PuO/sub 2/ powders indicated that variations in the processing variables can affect the final product. Measurements with the B. E. T. and Innes apparatus confirmed that the specific surface area of the initial batch of the PuO/sub 2/ powder had increased appreciably during storage. Deltatherm differential thermal analysis apparatus was checked out. Procedures were devised for the determination of plutonium and uranium. Sintering studies were continued for pure PuO/sub 2/, and sintering trials were begun for mechanically mixed and coprecipitated PuO/sub 2/ and UO/sub 2/. Metallographic examinations of PuO/sub 2/ sintered pellets revealed a microstructural feature similar to eutectoid structures in alloys. Mechanical packing experiments were carried out using crushed UO/sub 2/ pellets fired to high density. Plasma torch production of UO/ sub 2/ indicates that excellent spheroidization is attained, but central voids were found in the pellets. Reactor physics studies were completed for the analysis of the potential of plutonium as a fuel in near-thermal converter and straight burner reactors. Plutonium was shown to be promising …
Date:
October 31, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
THE EFFECTS OF INTERNAL HEAT GENERATION ON POT CALCINATION RATES FOR RADIOACTIVE WASTES
Methods by which the radial deposition mechanism was determined in experiments with simulated waste solutions are reviewed. Based on this mechanism, an expression for the rate of solid deposition with internal heat generation was developed by a combined heat and material balance. A sample calculation for Purex waste showed that a moderate heat generation rate of 5000 Btu/hr/ft/sup 3/ would decrease the time to fill a 12-in.-dia calcination vessel from 78 to 55 hr. For the calcination stage of the process in which the deposited solids are heated in the absence of a liquid phase, a solution was developed for the equation of heat transfer with the temperature profile from the solid deposition stage as an initial condition. For the example Purex waste with a heat generation rate of 5000 Btu/hr ft/sup 3/, less than 15 min would be required for calcination, compared to about 8 hr in experiments with simulated wastes. (auth)
Date:
October 23, 1961
Creator:
Perona, J.J.
Object Type:
Report
System:
The UNT Digital Library
Upper Atmosphere Re-Entry Study High Altitude Burnup. Volume 2
Methods of determining the fate of radioactive fuels in space power units burned up on re-entry into the earth's atmosphere are reviewed. Particulate characteristics experiments were derived from an analytical study on the ablation of Dlutonium fuel. This study revealed that the particulate size distribution resulting on re-entry burnup is a function of: the fuel form in use and the material velocity and atmospheric density at the time the fuel is exposed. The particulate fate experiments were derived essentially from studies of the effects of thermal and turbulent diffusion, and wind and gravity dispersion on the particulate cloud. The experiments recommended are described. (M.C.G.)
Date:
January 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A Theoretical Study of the Transient Operation and Stability of Two-Phase Natural Circulation Loops
Mathematical models of the time-dependent behavior of two-phase natural- circulation loops were used to predict the operation and to explain the unusual instability sometimes observed. The initial results obtained for a loop similar to the Univ. of Minnesota loop were used to formulate a more complex and accurate model, and the predicted transient behavior was in close agreement with the experimental results from the Minnesota loop. For a 300psia, high-pressure loop, unstable oscillatory behavior was predicted under certain conditions and stable behavior under others. Closed unstable regions rather than limits were predicted, and the specifications of stability in terms of a single parameter were found to be impossible. The great difference in oscillatory frequencies observed at low and high pressures was found to be due largely to the system geometry. The criterion for the absence of oscillations was found to be similar to one of the criteria for stability of chemical reaction systems. (D.L.C.)
Date:
June 1, 1961
Creator:
Garlid, K.; Amundson, N. R. & Isbin, H. S.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library