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Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961 (open access)

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 (open access)

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
Measurement of Xenon Poisoning in the HRT (open access)

Measurement of Xenon Poisoning in the HRT

Measurements obtained during three periods of HRT operations indicated that the xenon poison fraction was approximately 0.010. The technique used was based on mass spectrographic analyses of the stable xenon isotopes in the reactor off-gas stream. Models proposed to explain the measurements show that xenon, which is formed primarily by decay of iodine adsorbed on the pipe walls, is held up on the walls, out of the circulating stream, for an average period of about eight hours. (auth)
Date: April 19, 1962
Creator: Burch, W.D.
Object Type: Report
System: The UNT Digital Library
The Measurement of Energy and Intensity of Gamma Rays by Use of a Scintillation Spectrometer (open access)

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
Reactor Development Program Progress Report, March 1962 (open access)

Reactor Development Program Progress Report, March 1962

ABS>Developmental work is reported on the EBWR and Borax-V other general development work is reported in the area of liquid metal cooled reactors and particularly on the EBR-I and H, and the fast reactor test facility. General reactor technological development is described on applied reactor physics, reactor fuels development, reactor materials development, heat engineering and fluid flow, chemical separations, advanced systems, and nuclear safety. (J.R.D.)
Date: April 15, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Crystallographic D-Space Computer Program (open access)

Crystallographic D-Space Computer Program

D-Space is a computer program which generates indices (hld), tests for space-group extinctions, and calculates d,'' 1/d/sup 2/, sin theta , sin/sup 2/ theta , sin theta / lambda , sin/sub 2/ theta / lambda /sup 2/, theta , and 2 theta for any crystal system and space group, requiring only the unit cell constants as data input. Optional calculations are the single-crystal angle settings, phi and chi, and various Lorentz and Lorentz-polarization corrections. (auth)
Date: April 1962
Creator: Mueller, M. H.; Meyer, E. F. H. & Simonsen, S. H.
Object Type: Report
System: The UNT Digital Library
Radiation Problems Associated With the Handling of the Actinide Elements (open access)

Radiation Problems Associated With the Handling of the Actinide Elements

The hazards connected with the handling of actinide elements are surveyed. Emphasis is placed on Th, U, Np, and Pu. It is pointed out that the chemical toxicity of the actinides is usually minor when compared with radiochemi cal toxicity. Inhalation and ingestion are the important routes of entry but direct injection into the blood stream through wounds also requires consideration. Special enclosures, such as glove boxes, function primarily to minimize the risk of inhalation and aid in confinement. The external hazard from actinide elements, primarily due to gamma and fast neutron emission, varies considerably with the element and its source. Irradiated actinides, such as Th and Pu, usually show an increase in the external hazard from gamma radiation with extent of irradiation. (C.H.)
Date: April 1, 1962
Creator: Steindler, M.J.
Object Type: Report
System: The UNT Digital Library
A FORTRAN Program for Calculating Single Crystal Absorption Corrections (open access)

A FORTRAN Program for Calculating Single Crystal Absorption Corrections

A Fortran program is described for calculating the absorption correction for application to single crystal x ray or neutron intensity measurements. The program is available in the form of symbolic punched cards. InstrucPions are included. (J.R.D.)
Date: April 1, 1962
Creator: Wehe, D. J.; Busing, W. R. & Levy, H. A.
Object Type: Report
System: The UNT Digital Library
RADIOISOTOPES AND RADIATION APPLICATIONS. Quarterly Progress Report No. 12 (open access)

RADIOISOTOPES AND RADIATION APPLICATIONS. Quarterly Progress Report No. 12

Continued research is reported in the areas of intrinsic radioactive tracers for industrial process control and the effects of structural factors on radioinduced graft polymerization. The use of Be-- Po neutron sources for production of short-lived isotopes is being investigated. Data are included on the effects of target volume, high-Z scattering media, target-isotope concentration, and macroscopic cross-section on speciflc and total activation produced with a 10-curie source. Research on graft-polyerization concerning the effects of structure on freetinued. Results indicate that the radical formed in a variety of substituted methacrylate polymers is the same in all cases. (J.R.D.)
Date: April 18, 1962
Creator: Sunderman, D.N. ed.
Object Type: Report
System: The UNT Digital Library
Stress and Deflection of Boiler Fuel Element Boxes (open access)

Stress and Deflection of Boiler Fuel Element Boxes

Equations were derived by strain-energy methods for analyzing the stress and deflection in the boiler fuel element boxes used in the Pathfinder nuclear reactor. These boxes are of two types, both constructed of Zircaloy lI. One box is approximately 5 in. sq. The second is approximately 10 1/2 in. sq divided internally into four compartments (5 in. sq) by a cruciform control-rod guide structure. Stress and deflection in the box walls are caused by pressure differences across the walls. The equations were verified by testing an aluminum model of the single-element box and a Plexiglas model of the four-element box. There was less than 10% difference between theoretical and measured values for the maximum stress and deflection, and therefore, use of the equations for designing the Pathfinder fuel element boxes is justified. (auth)
Date: April 13, 1962
Creator: Vlies, L. E.
Object Type: Report
System: The UNT Digital Library
NEUTRON THERMALIZATION MEASUREMENTS USING AN ELECTRON LINEAR ACCELERATOR (open access)

NEUTRON THERMALIZATION MEASUREMENTS USING AN ELECTRON LINEAR ACCELERATOR

Discussions are presented concerning integral experiments primarily on water and graphite systems. A description of experimental facilities is included along with details of die-away experiments, infinite-medium spectrum measurements, spatially dependent spectrum measurements, spectrum measurements for graphite systems, and development of a subcritical assembly program. (J.R.D.)
Date: April 10, 1962
Creator: Beyster, J R
Object Type: Report
System: The UNT Digital Library
A STUDY OF THE SHIELD OF THE UNIVERSITY OF ILLINOIS TRIGA MARK II RESEARCH REACTOR (open access)

A STUDY OF THE SHIELD OF THE UNIVERSITY OF ILLINOIS TRIGA MARK II RESEARCH REACTOR

Detailed measurements were made of the fast-neutron and gamma dose rates and the thermal-neutron fluxes existing at the surfaces of the biological shield of the University of Illinois TRIGA Mark II Research Reactor. Dose rates and fluxes were found to be extremely low. A comparison was made by means of threshold foil techniques between the fast-neutron flux in a beam hole of the reactor during steady-state operation at 1 kw and during a nominal 250 Mw, 30 msec pulse produced by rapid insertion of approximates two dollars of excess reactivity. The flux over the duration of the pulse was approximately four times that for steady-state operation for 1 hr at 1 kw. Fast-neutron dose rates and thermal-neutron fluxes were measured at each of the four beam ports of the reactor at operating powers of 0, 1, and 5 watts. Some gamma dose rate data was also obtained at 0 and 1 watt. The threshold foil technique used is described. (auth)
Date: April 23, 1962
Creator: Blosser, T.V.; Freestone, R.M. Jr. & Miller, J.M.
Object Type: Report
System: The UNT Digital Library
Specifications and Fabrication Procedures for Type 3 Neutron Absorber Sections (open access)

Specifications and Fabrication Procedures for Type 3 Neutron Absorber Sections

The specification contains information concerning the material, process, and product requirements to be met by the fabricator. (J.R.D.)
Date: April 25, 1962
Creator: Edgar, E. C. & Clayton, H. R.
Object Type: Report
System: The UNT Digital Library
A PINHOLE CAMERA AUTORADIOGRAPHIC TECHNIQUE FOR ENCAPSULATED IRRADIATED FUEL SPECIMENS (open access)

A PINHOLE CAMERA AUTORADIOGRAPHIC TECHNIQUE FOR ENCAPSULATED IRRADIATED FUEL SPECIMENS

A gamma pinhole camera was devised to permit a nondestructive examination of irradiated specimens while still in sealed capsules. The camera was designed such that a complete experiment may be withdrawn from an irradiation facility, the specimen autoradiographed, and the experiment then reinserted if so desired. The pinhole aperture is 0.020 in., and the source to pinhole block is 4 ft. The image-to-source sizes are a one-to-one ratio. The resolution of the image is 0.03 in. (auth)
Date: April 1, 1962
Creator: Beck, W.N.
Object Type: Report
System: The UNT Digital Library
CHEMICAL PROCESSING OF COATED PARTICLE FUELS (open access)

CHEMICAL PROCESSING OF COATED PARTICLE FUELS

BS>Laboratory studies on the processing of graphite-base fuel elements containing pyrolytic carbon- or Al/sub 2/O/sub 3/-coated particles are reviewed. Potential processes for recovering U and Th from irradiated elements include grinding followed by acid leaching, and, burning and subsequent dissolution of the oxide ash. Disintegration in 90% HNO/sub 3/ was briefly evaluated as a method for determining the integrity of coated particles dispersed in graphite matrices. (auth)
Date: April 1, 1962
Creator: Ferris, L.M.
Object Type: Report
System: The UNT Digital Library
MODIFICATION OF THE EXPERIMENTAL BOILING WATER REACTOR (EBWR) FOR HIGHER- POWER OPERATION (open access)

MODIFICATION OF THE EXPERIMENTAL BOILING WATER REACTOR (EBWR) FOR HIGHER- POWER OPERATION

Supplement to ANL-5607. Alterations and additions made to the Experimental Boiling Water Reactor (EBWR) plant to permit operation at power levels up to I00 Mw(t) are described. Topics covered include over-all system modifications and additions, nuclear component modifications and additions, and reboiler plant component description. (M.C.G.)
Date: April 1, 1962
Creator: Matousek, J.F. comp.
Object Type: Report
System: The UNT Digital Library
Kinetic Studies of the Reactions Occurring Between Tungsten and Gases at Low Pressure and High Temperatures (open access)

Kinetic Studies of the Reactions Occurring Between Tungsten and Gases at Low Pressure and High Temperatures

Oxygen, nitrogen, and nitric oxide gases were passed through a system consisting of a tungsten filament, an ion gauge, and a mass spectrometer. The ion gauge recorded total pressures and the spectrometer recorded partlal pressures of O/sub 2/, N/sub 2/, NO, CO, COa, and H/sub 2/O. From the way these pressures changed with filamert temperature, the rates of conversion of O/sub 2/ to volatile tungsten oxides and O, and of NO to volatile tungsten oxides N/sub 2/ , O/sub 2/, and O were computed. The time rate of resistance change in the filament was used to compute the rate of conversion of tungsten to tungsten oxides. The filament temperatures ranged from 1950 through 2600 deg K and gas pressures ranged from 10/sup -8/ to 10/sup -6/ atm. For the tungsten-oxygen reaction, the rates of tungsten and oxygen loss were found to depend upon oxygen atom concentration on the surface. The rate of oxide power, depending upon the concentration of oxygen atoms on the surface. The reaction rate at constant oxygen pressure decreases with increasing temperature. For calculational purposes, the tungsten oxygen gas moleeules were assumed to be WO/sub 3/ only, though WO/sub 2/ and WO are other possible products. The …
Date: April 1, 1962
Creator: Anderson, H. U.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
SODIUM MASS TRANSFER: III. THE APPLICATION OF LIQUID AMMONIA AS A SODIUM LEACHING AGENT (open access)

SODIUM MASS TRANSFER: III. THE APPLICATION OF LIQUID AMMONIA AS A SODIUM LEACHING AGENT

A technique is presented for liquid ammonla leaching of metallic sodium from corrosion coupons, filter elements, and sodium samples to reveal contaminants and impurities. The advantages of the method in preserving the physical form of corrosion or mass-transfer deposits are demonstrated. A possible application to the determination of trace oxygen in sodium is mentioned. (auth)
Date: April 1962
Creator: Alter, H.W. & McManus, P.A.
Object Type: Report
System: The UNT Digital Library
An Investigation of the Corrosion Resistance of Brazing Alloys for Austenitic Stainless Steel Fuel Elements for Service in 565 F Pressurized Water (open access)

An Investigation of the Corrosion Resistance of Brazing Alloys for Austenitic Stainless Steel Fuel Elements for Service in 565 F Pressurized Water

Since brazing was the method selected for joining the stainless steel SM- l reactor fuel element, corrosion studies were conducted on various potential brazing alloys to evaluate their resistance under the approximate pressurized- water conditions of the SM-1. The program consisted mainly of testing type 304L stainless steel T'' joints brazed with selected alloys in quiescent, degassed, and deionized autoclaved water at 565 deg F under 1200-psi pressure. In the initial phase of the investigation, tests were limited in duration to l000 hr in order to quickly screen some 18 potential alloys for longer time testing. Based on weight-change data and the metallographic examinations, five of the 18 alloys exhibited sufficient corrosion resistance to warrant further investigation. These alloys were subjected to autoclave tests of 12 and 16 months. In these extended tests, 1 cc O/sub 2/liter and a mixture of 1 cc O/sub 2/liter plus 50 cc H/sub 2/liter, respectively, were added to the water to more closely simulate SM- 1 reactor water conditions and to evaluate the effect of different gaseous additions on the corrosion behavior of the alloys. On the basis of weight-change data and metallographic examination after long-term exposure of the tested stainless steel-base joint; these …
Date: April 12, 1962
Creator: Beaver, R. J.; Leitten, C. F. Jr. & English, J. L.
Object Type: Report
System: The UNT Digital Library
STABILIZING SRE FUEL ELEMENTS (open access)

STABILIZING SRE FUEL ELEMENTS

None
Date: April 15, 1962
Creator: Donohue, H.F. & Vislay, H.A.
Object Type: Report
System: The UNT Digital Library
STATUS REPORT NO. 2 ON CLINCH RIVER STUDY (open access)

STATUS REPORT NO. 2 ON CLINCH RIVER STUDY

None
Date: April 13, 1962
Creator: Morton, R.J. ed.
Object Type: Report
System: The UNT Digital Library
IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR (open access)

IRRADIATION OF A U-2% Zr FUEL TUBE IN THE VBWR

A coextruded 2-inch-diameter tubular fuel element of U-2 wt% Zr alloy clad with Zircaloy-2 was irradiated in the Vallecitos Boiling Water Reactor to 1280 Mwd/t burnup with a maximum core temperature of 433 deg C. The purpose of this irradiation was to determine the dimensional stability of the alloy under conditions approaching those contemplated for D/sub 2/O-cooled power reactors. Successive dimensional measurements revealed a sharp change in swelling rate between 700 and 1280 Mwd/t burnup. The amount of swelling increased during this interval from 0.8 to 3.6% (0.7% final cladding strain). This test indicated that the dimensional stability of the U-2 wt% Zr alloy is inferior to that of unalloyed U irradiated under similar conditions. (auth)
Date: April 1, 1962
Creator: Quigley, H.C.
Object Type: Report
System: The UNT Digital Library
PL-3 Project Quarterly Progress Report, January 1, 1962-March 31, 1962 (open access)

PL-3 Project Quarterly Progress Report, January 1, 1962-March 31, 1962

Progress is reported on phase II in sections on final design, procurement, fabrication, testing, packaging, and crew training. A summary of completed phase I work on concept evaluation and preliminary design is also included. (J.R.D.)
Date: April 10, 1962
Creator: Humphries, G. E.
Object Type: Report
System: The UNT Digital Library
Specifications and Fabrication Procedures for Type 3 Fuel Elements (open access)

Specifications and Fabrication Procedures for Type 3 Fuel Elements

Process and product requirements to be met in the fabrication of Type 3 fuel elements are presented. The fuel elements specified consist of thin plates of a dispersion of highly enriched UO/sub 2/ and ZrB/sub 2/ in a stainless steel matrix which is clad with stainless steel on all surfaces. Quality assurance provisions are discussed. Process and material specifications and packaging and packing for shipment are described. Sample calculations and drawings are included. (M.C.G.)
Date: April 27, 1962
Creator: Edgar, E. C. & Clayton, H. R.
Object Type: Report
System: The UNT Digital Library