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Preparation of Charge Materials for Ornl Electromagnetic Isotope Separators
SEPARATORS. C. W. Sheridan, H. R. Gwinn, and L. O. Descriptions are given of procedures, techniques, and equipment used to prepare charge materials for electromagnetic isotope separators at ORNL. Data on ion outputs during processing, charge consumption rates, and process efficiencies are given for 54 elements. (auth)
Date:
August 1, 1962
Creator:
Sheridan, C W; Gwinn, H R & Love, L O
Object Type:
Report
System:
The UNT Digital Library
Strontium-90 Fueled Thermoelectric Generator Power Source for Five-Watt U.S. Coast Guard Light Buoy. Final Report
The objectives of the SNAP 7A program were to design, manufacture, test, and deliver a five-watt electric generation system for a U. S. Coast Guard 8 x 26E light buoy. The 10-watt Sr/sup 90/ thermoelectric generator, the d-c-to-d-c converter, batteries and the method of installation in the light buoy are describcd. The SNAP 7A generator was fueled with four capsules containing a total of 40,800 curies of Sr/sup 90/ titanate. After fueling and testing, the SNAP 7A electric generating system was installed in the Coast Guard light buoy at Baltimore, Maryland, on December 15, 1961. Operation of the buoy lamp is continuous. (auth)
Date:
February 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1961
Progress is reported on investigations in support of the Experimental Gas-Cooled Reactor, the Pebble-Bed Reactor Experiment, Advanced reactor design and development, test facilities, components, and materials. Topics covered include EGCR physics, EGCR performance analyses, structural investigations, EGCR component and materials development and testing, EGCR experimental facilities, PBRE physics and design studies, fueled-graphite investigations, clad fuel development, design studies of advanced power plants, experimental investigations of heat transfer and fluid flow, development of equipment anmd test facilities. and fabrication studies. (M.C.G.)
Date:
February 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Examination of Uranium-2 w/o Zirconium Experimental Fuel Slugs Irradiated in EBR-I. Final Report-Program 6.1.11
Six groups of U-2 wt% Zr fuel slugs were irradiated in the first core of the EBR-I to burnups of 0.080 to 0.189 at.% at calculated temperatures of 307 to 353 deg C. Two groups of cast specimens were found to be more dimensionally stable than four groups of wrought slugs. Of the wrought slungs, the as quenched group showed less tendency to grow than the three groups which had some annealing after quenching. Specimens at burnups of about 0.189 at.% and at 383 deg C showed the onset of swelling as indicated by density measurements. The hardnesses of these specimens seemed but little affected by radiation, but there was an indication of softening with increasing irradiation temperature. (auth)
Date:
February 1, 1962
Creator:
Murphy, W. F.; Klank, A. C. & Paine, S. H.
Object Type:
Report
System:
The UNT Digital Library
Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961
Nine samples of ThO/sub 2/ -UO/sub 2/ prepared as part of the solgel process development studies showed no consistent effects from small variations in several process parameters. The reaction of methane and copper oxide was studied. Engineering studies of the continuous dissolution of simulated U-Zr-Sn fuels in 6.5 M NH4F, 0.6-1.0 M NH/sub 4/NO/sub 3/, 0.1 M H/sub 2/O/sub 2/ were continued in modified 6-in.-dia. equipment. A total of 1642 kg of U from NaK bonded SRE Core I fuel rods wad dejacketed to date/su Initial operability tests of the 250 ton prototype shear unit showed a number of minor modifications are warranted. Center tube temperatures measured in a vertical 64 tube electrically heated simulated fuel element bundle were very near those previously obtained in the horizontal position. A 304 SS tube containing eutectic NaK was dissolved by HF in fused saIt at a tube wall penetration rate of approximates 2 mils/hr. Partial differential equations were derived from the concentration of unreacted UF/sub 6/ as a function of time and position in a sphere of NaF during sorption of UF/sub 6/. Calcium nitrate solution was added directly to the pot calciner during Purex feeding to give smoother operation of the …
Date:
April 1, 1962
Creator:
Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type:
Report
System:
The UNT Digital Library
Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre
The IBM 7090 program Murgatroyd is a revised and extended version of the IBM 704 program PET-I, which solves (by a fifth-order Runge-Kutta procedure) the coupled firstorder differential equations for power, delayed neutron concentration, and temperature in a one-region reactor as a function of time, given an input reactivity variation represented by a series of linear ramps. The basic extensions were those which were necessary to include the effects of the separate heat capacities and temperature coefficients of the fuel sait and graphite in the MSRE, and of heat transfer between the fuel and graphite. In addition, the input and output sections of the previous program were modified to facilitate the use of the program in extensive parameter studies, and a calculation of the pressure rise in the core was included. Typical running times are of the order of l2 milliseconds per time step; a calculation of a 30-second power history using a 10 millisecond time step requires about 36 seconds of machine time. (auth)
Date:
April 1, 1962
Creator:
Nestor, C. W. Jr.
Object Type:
Report
System:
The UNT Digital Library
BRAZING OF CERAMICS. Progress Report
Brazing alloys such as 48 Ti-48 Zr-4 Be (wt%) and 49 Ti-49 Cu-2 Be (wt%) have been found to readily flow on oxide and graphite ceramics. Two demonstrati on fuel element assemblies were fabricated to illustrate the usefulness of these procedures for nuclear applications. One of these assemblies contained graphite tubes and end caps which were brazed to a molybdenum hanger. The second demonstration fuel element was composed of a compartmented aluminum oxide plate to which aluminum oxide cover plates were brazed. (R.J.S.)
Date:
November 1, 1962
Creator:
Fox, C.W.
Object Type:
Report
System:
The UNT Digital Library
The Effects of Irradiation on Some Binary Alloys of Thorium-Plutonium and Zirconium-Plutonium
A specimen of cast thorium-5 wt% plutonium and one of thorium-10 wt% plutonium were irradiated to total atom burnups of 1.9 and 2.6%, respectively, at maximum fuel temperatures of approximately 450 deg C. Both alloys displayed excellent dimensional stability with volume increases of 0.8 and 1.2% per atom per cent burnup, respectively. Three cold-rolled specimens of zirconium-5 wt% plutonium and one cold-rolled specimen of zirconium-7 wt% plutonium were also irradiated. The zirconium- plutonium alloy specimens all showed extremely poor dimensional stability, with anisotropic elongations ranging from approximately 100 to 500%. The irradiation growth coefficients for these specimens ranged from 90 to 210 microinches per inch per atom per cent burnup. The poor dimensional stability of the zirconium-- plutonium alloy specimens is attributed to a highly preferred grain orientation that presumably developed during cold rolling. (auth)
Date:
July 1, 1962
Creator:
Horak, J. A.; Kittel, J. H. & Rhude, H. V.
Object Type:
Report
System:
The UNT Digital Library
The Electrical Resistivity of Molten and Solid Thorium-Magnesium Eutetic
Electrical resistivity properties of polycrystalline 39 wt % thorium-- magnesium eutectic are reported for the solid from room temperature to its melting point at 589 deg C and as a liquid from its melting point to 900 deg C. The electrical resistivity of the eutectic at the melting point was 69.5 microhm- centimeters; it decreased to a value of 64.8 microhm-centimeters at 900 C. Tantalum tubing was used to contain the alloy in the molten state. (auth)
Date:
May 1, 1962
Creator:
Provow, D. M. & Fisher, R. W.
Object Type:
Report
System:
The UNT Digital Library
A Study of the Kinetic and Mechanical Properties of a Stabilized Beta Phase Plutonium Alloy
The elements Sn, Mg, Ti, Zr, Hf, Si, Cd, and U were alloyed with plutonium to determine their effect on stabilization of the beta phase. Zirconium was found to be the ' most effective. Kinetic studies were conducted on Pu-Zr alloys having 0.24, 0.65, and 1.7 at.% Zr contents. The beta to alpha transformation in the Pu-Zr alloys was somewhat similar to that in unalloyed plutonium. The main difference being that time, temperature, transformation curves of the alloys were shifted to the right as the zirconium concentration increased. It was determined that the amount of beta phase retained at room temperature increased as the zirconium concentration increased. The minimum amount of Zr needed to stabilize the beta phase of plutonium at room temperature was determined to be 2.0 at.%. A 2.4 at.% Zr addition stabilized the beta phase of plutonium at atmospheric pressure from room temperature to 265 deg C. During mechanical property testing it was determined that the stabilized beta Pu-2.4 at.% Zr alloy was brittle from room temperature to 230 deg C. Both tensile and compression strengths of the beta stabilized alloy were greater than the unalloyed beta phase of plutonium. A brittle-ductile transition was noted between 130 …
Date:
January 1, 1962
Creator:
Taylor, J. M.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
The Measurement of Energy and Intensity of Gamma Rays by Use of a Scintillation Spectrometer
The analysis of gamma-ray spectra measured with a scintillation counter with an anticoincidence annulus is described in detail. In particular the problem of the determination of the energy and intensity of gamma rays from such measurements is considered. The shapes of the full-energy peaks in observed complex spectra are studied and an attempt is made to justify their description in terms of a Gaussian response function. The details of the statistical analysis of complex gamma-ray spectra are given and, finally, procedures which have been used to confirm the validity of error estimates in energy and intensity measurements are described. (auth)
Date:
April 1, 1962
Creator:
Julke, R. T.; Monahan, J. E.; Raboy, S. & Trail, C. C.
Object Type:
Report
System:
The UNT Digital Library
Criteria for the Design of the Thorium Fuel Cycle Development Facility
Criteria for the conceptual design of the proposed Thorium Fuel Cycle Development Facility to be located at the Oak Ridge National Laboratory were established and are presented. In addition, conceptual layouts of the building and equipment are included. Reference fuel elements and processes that were selected as a basis for developing criteria for the facility are described. (auth)
Date:
March 1, 1962
Creator:
Irvine, A.R. & Lotts, A.L.
Object Type:
Report
System:
The UNT Digital Library
KINETIC EXPERIMENTS ON WATER BOILERS-"A" CORE REPORT-PART II. ANALYSIS OF RESULTS
The status of the analytic portion of the KEWB program at the time of completion of the spherical core experiments is summarized. Three computer programs were developed for use in this analytic effort. The first reassembles and smooths three decades of reactor power data read separately from oscillogram records of reactor excursions. It then computes the logarithmic derivative of the power, energy release, fuel solution temperature, and temperature compensated reactivity. The second program utilizes the space-independent neutron kinetics equations with any number of delayed neutron groups to determine the reactivity in the reactor from the power and its derivative. The third program solves the space-independent kinetics equations for the neutron flux from an input reactivity or initial period. Up to 50 reactivity feedback equations includirg delayed neutrons are provided for in this program. A mathematical model of the reactor investigated extensively was one containing six delayed neutron groups, conventional treatment of temperature reactivity compensation, and void compensation of reactivity induced by radiolytic gas void growth proportional to the product of reactor power and energy release. Partial mathematical solutions to the kinetic equations were derived for reactivity feedback proportional to prompt temperature and void growth according to the product of power …
Date:
February 1, 1962
Creator:
Dunenfeld, M. comp.
Object Type:
Report
System:
The UNT Digital Library
Measurements and Changes on SM-1 Core II During Period October 1, 1961 to May 30, 1962
Tests at the SM-1 reactor are reported for the period October 1, 1961, to May 31, 1962. Loading changes were made in SM-1 Core II during the scheduled semiannual shutdowns in October to November 1961 and April to May 1962. Core physics tests include control rod bank calibrations, bank position at several temperature and xenon poison conditions vs core changes and energy release, shutdown neutron source decay and startup channel testing, and critical rod positions for stuck rod configurations. Shielding measurements of gamma radiation in the rod drive pit were made, and dose rates from spent fuel elements as a function of the depth of the water shield were obtained. A lift mechanism for the BF/sub 3/ detector of one startup channel was installed and preliminary testing completed. Water chemistry and radiochemistry tests included a changeover to high pH for the primary coolant, fission product monitoring for iodine, measurement of dose rates on primary system during shutdown, radiochemical analysis of primary water and crud, and change of metal corrosion samples. Buildup of radioactivity in the demineralizer was monitored by radiation surveys and film badge exposures. (auth)
Date:
July 1, 1962
Creator:
Motte, F. G.; Best, W. C. & Kortheuer, J. D.
Object Type:
Report
System:
The UNT Digital Library
CORE A CRITICAL STUDIES FOR THE ENRICO FERMI ATOMIC POWER PLANT ON ZPR-III
A critical studies program for the Enrico Fermi Atomic Power Plant was run with the ZPR-III fast critical facility. The objectives of this program included determination of the U enrichment required for criticality, the effect of minor variations in core and blanket composition, reactivity coefficients, control and safety rod characteristics, power distribution, spectral indices, and the reactivity worth and wave shape of the oscillator rod. The experimental program was separated into two phases. The first phase involved investigatlona of a clean assembly, which was a simplified and homogenized core and blanket geometry constructed for ease of experimental manipulation and analysis. The second phase involved experiments on the engineered, or as-designed, core. This assembly included such engineering details as control and safety rod channels, core end gaps, and a precise reconstruction of the core outline. This provided detailed information on worths of control rods and fuel subassemblies, power distribution, and the effect of variations in core and end-gap dimensions. The application of critical experiment data to the determination of the Enrico Fermi reactor characteristics has established the U/sup 235/ enrichment for the fuel alloy, worths of fuel subassemblies, and the B/sup 10/ enrichment for the control and safety rods. In addition, …
Date:
October 1, 1962
Creator:
Branyan, C.E.
Object Type:
Report
System:
The UNT Digital Library
PHYSICS ANALYSIS OF THE JUGGERNAUT REACTOR
The JUGGERNAUT is an intermediate-power research reactor designed and constructed as a supporting facility for chemistry and physics research. The design of this reactor is similar to that of the ARGONAUT, and those methods of evaluating the nuclear characteristics of the ARGONAUT which gave good agreement with experimental data were considered applicable to the analysis of the JUGGERNAUT. The analyses for both the JUGGERNAUT and the ARGONAUT were based on a modified two-group theory. The criticality calculations were carried out with the 1BM704 and the two-dimensional PDQ code. Reactivity effects were calculated by hand by means of perturbation techniques, with the real and adjoint fluxes obtained from PDQ calculations. (J.R.D.)
Date:
July 1, 1962
Creator:
Moon, D.P.
Object Type:
Report
System:
The UNT Digital Library
2D PERT. A TWO-DIMENSIONAL PERTURBATION CODE
Given multigroup fluxes and adjoint fluxes of any cylindrical R-Z configuration, 2D PERT may compute: the prompt-neutron lifetime; the relative worth of various delayed neutrons; the integrals of capture, fission, etc., of given materials over any given region; local perturbations, i.e., danger coefflcients; and integrated perturbations, i.e., reactivity effect of uniform variation in the cross sections affecting a whole region. 2D PERT is programmed for a 32K IBM-704 using 3 tape units. The code is written in FORTRAN with the exception of two SAP subroutines. Input fluxes and adjoint fluxes are on tapes which may be obtained either directly from CUREM output or manufactured by a special tape-writing routine. Homogeneous cross sections and variations of these cross sections are either read in as input information or are computed by the code from a microscopic-cross-section library and atomic densities given as input. A combination of these methods may be used. (auth)
Date:
May 1, 1962
Creator:
Chaumont, J. M. & Koerner, J. A.
Object Type:
Report
System:
The UNT Digital Library
EQUIPOISE 3A
None
Date:
June 1, 1962
Creator:
Nestor, C. W. Jr.
Object Type:
Report
System:
The UNT Digital Library
THE THEORY AND MEASUREMENT OF CRITICALITY
ABS>The measurable properties of a critical assembly (e.g.. fission, capture, and leakage rates; neutron-per-fission ratios; bare/Cd-covered reaction rate of-atios; danger eoefficients; etc.), whose judicious use completely defines tbcneutron economy in the assembly, are discussed. Require ments regarding the internal consisteney of these of:deasured quantities are reviewed. lt is concluded that theoretical analysis of the assembly must both reproduce the gross experimental results and reflect the internal consistency of the data. Only thermal systems fueled with U/sup 235/ and U/sup 238/ are considered. (T.F.H.)
Date:
January 1, 1962
Creator:
Kelber, C.N.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Heat Rejection Systems for PL-3
An investigation was made of heat rejection systems for use in the PL-3 nuclear power plant, designed for placement at Byrd Station, Antarctica. It was concluded that the glycol-coupled surface condenser and air blast cooler combination appears to be suited for PL-3 plant requirements and operating conditions. (auth)
Date:
March 1, 1962
Creator:
Thurnau, C. J.
Object Type:
Report
System:
The UNT Digital Library
COMPILER INTO GEORGE ASSEMBLY ROUTINE
This program of the GEORGE Assembly Routine (GAR) will accept Fortran- like statements from paper tape and create the GAR language program on tape. This includes the needed calls for common subroutines and the reservations for the named variables and temporaries. The original statements in Fortran are carried along as remarks. The GAR language program may then be processed in the usual way by the GEORGE Assembly Routine, giving machine-language code. The level of sophistication of the source language is roughly equal to that of Fortransit or SALT. (auth)
Date:
June 1, 1962
Creator:
George, R.
Object Type:
Report
System:
The UNT Digital Library
Spent Fuel Transfer, Storage and Shipment for PL-3
In refueling development studies performed on PL-3 Phase I design, several methods of fuel transfer, storage, and shipment were investigated. An evaluation of the relative merits of the systems and designs under study, as applied to either the BWR or PWR concepts, is made and optimum designs are selected. An analysis of spent fuel shipping cask shielding requirements is presented, along with recommendations for future study in this area. (auth)
Date:
March 1, 1962
Creator:
Hauenstein, G. C. & Pomeroy, D. L.
Object Type:
Report
System:
The UNT Digital Library
Evaluation of Subsize Izod Specimen Designs for Determining the Notch Toughness of Zircaloy-2
Correlations were made on Zircaloy-2 Izod impact data and Charpy-V drop- weight data. Subsize Izod impact specimens of various geometries and notch configurations and standard ASTM Charpy-V specimens were prepared from bar and plate stock and tested. Drop-weight tests were also conducted and the NDT (nil- ductility transition) temperature was determined for 1/2 in. Zircaloy-2 plate. Results show that the impact properties of Zircaloy-2 are sensitive to hydrogen concentration, specimen and notch geometry, and specimen and notch orientation. No subsize specimen design was found which yielded impact curves similar to those obtained with standard Charpy-V notch specimens, but designs suitable for in- pile testing were found. It was found that Zircaloy-2 has the property of arresting a moving crack even at temperatures of --100 deg C and lower. (P.C.H.)
Date:
October 1, 1962
Creator:
Prislinger, J. J.
Object Type:
Report
System:
The UNT Digital Library
Physics Division Summary Report
The use and operation of the 4.5-Mev Van de Graaff generator ts descrtbed. Sputtering experiments were conducted by bombarding single crystals of electrolytic copper wtth deuterons with energies of 0.8 to 2.5 Mev. The experimental results are discussed on the basis of existing sputtering theories. The kinetic-energy distribution and Boltzmann "temperatures" of most of the fragments of cyanogen under electron impact were determined. A lower limit of 0.05 ev for this temperature'' was also determined for the mass spectrometer. A statistical theory of nuclear forces was developed in close analogy with the statistical mechanics of Gibbs. The theory of Byers and Yang was improved by removing the special assumption of cylindrical symmetry and the assumption of independentparticle motion. The safe assumption of time-reversal invariance was substituted for both. The quantum of trapped flux was found to be independent of the shape of the superconducting ring. The effective charge 2e was seen to result from the two-fold degeneracy induced by time-reversal invariance. It was observed that the same considerations which apply to the problem of flux quantization can be used to elucidate the gauge invariance of the theory of Bardeen, Cooper, and Schrieffer. Differences of total cross sections at high energies …
Date:
January 1, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library