Language

Chemical Technology Division, Unit Operations Section Monthly Progress Report, February 1962 (open access)

Chemical Technology Division, Unit Operations Section Monthly Progress Report, February 1962

In the operation of 6-in.-dia. foam-liquid columns, increase in either the liquid flow or foam flow caused increased channeling with increased HTU. Flooding values for the Immi mixer-settler were obtalned using the amine extraction final cycle Pu flowsheet. Two tests of the addltlon of uranyl nitrate to a thoria sol were made, one of which gave a good product and the other a product which disintegrated during calcination. Material balances for 22 waste calcination runs are summarized. (auth)
Date: August 23, 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
Chemical Technology Division, Unit Operations Section Monthly Progress Report, June 1961 (open access)

Chemical Technology Division, Unit Operations Section Monthly Progress Report, June 1961

An interfacial viseometer was built for use in an interfacial phenomena study. Installation of a 6-in.-ID foam separation column system was completed. The dispersiondrying-sintering characteristics of six low-nitrate batches of thoria sol material were studied. The average effective porosity of the CuO pellets used for reactor helium purification was determined to be 0.0545 for H/ sub 2/ transport and 0.0526 for CO transport. In continuous Zirflex dissolution studies, no H/sub 2/O/sub 2/ decomposition was observed when 10% H/sub 2/O/sup 2 was fed into boiling dissoivent through a water-cooled nozzle and the oxygen concentration in the scrubbed off-gas could be used to control the H/sub 2/O/sub 2/ concentration in the dissolver. The free fluoride in Zirflex solutions must be maintained above 1 molar in order to prevent uranium precipitation at low concentrations of uranium even though the F/sup -//U ratio exceeds 100. Chopped stainless steel-clad UO/sub 2/ sections were leached in a 4 stage pyrex leacher model using 6, 7, and 8 M nitric acid as the dissolvent. The temperature distribution expected within fuel elements consisting of square arrays of tubes was calculated for shipping conditions assuming heat to be transferred only by radiation. HETS values were calculated for uranium stripping …
Date: January 23, 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
A TRANSISTORIZED ALPHA COUNTER FOR AN ALPHA GAUGE (open access)

A TRANSISTORIZED ALPHA COUNTER FOR AN ALPHA GAUGE

A transistorized instrument prototype was designed and constructed to replace a vacuum-tube instrument in an alpha gauge, which measures the thickness density of gases. The instrument amplifies, shapes, discriminates, and counts alpha pulses from a Au-Si surface-barrier detector exposed to an alpha source in a gas-filled chamber. The circuit consists of a charge-sensitive preamplifier, a main amplifier with pulse clipping, a Schmitt trigger, a diode pump, and a count rate meter. Preliminary tests gave results comparable to the vacuum-tube instrument. Accuracy of counting was within 10% for 0.5- to 10-Mev alpha particles emitted at a maximum rate of 10/sup 6 per sec. The instrument was stable at 25 to 55 deg C, is small and portable, and costs less than 0. An infinitely thick, alpha source that will give a high count rate is being constructed for final tests. (auth)
Date: August 23, 1962
Creator: Kopp, M.C.
Object Type: Report
System: The UNT Digital Library
Migratory Agricultural Labor: References to Books, Periodicals, and Films, 1959-1969 (open access)

Migratory Agricultural Labor: References to Books, Periodicals, and Films, 1959-1969

This report and bibliography contains references to books, documentaries, and magazine articles that study migrant workers. It also contains information on specific issues that affect migratory agricultural workers, such as the Bracero program, the California grape strike, education, health, housing, and welfare, income, and more.
Date: June 23, 1969
Creator: Warnell, Katherine S.
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 (open access)

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
THE EFFECTS OF INTERNAL HEAT GENERATION ON POT CALCINATION RATES FOR RADIOACTIVE WASTES (open access)

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
Studies of Nuclear Resonant Absorption of Gamma Rays. Quarterly Report No. 4 Covering Period June 1, 1961 to August 31, 1961 (open access)

Studies of Nuclear Resonant Absorption of Gamma Rays. Quarterly Report No. 4 Covering Period June 1, 1961 to August 31, 1961

The effect of polarizing mngnetic field intensity on the nuclear resonant absorption was studied by varying the field strength at a 1-mc Co/sup 57/ source from 0 to 1000 gauss while keeping the absorber between the poles of a magnet having a fixed field of 800 gauss. The rates of resonance absorption change with field intensity were greatest in the region of 300 to 1000 gauss, and the% nuclear resonant absorption for 1000-gauss fields was 8.5 and 26% for perpendicular and parallel fields, respectively, as compared with 15% for no fields. Other absorption measurements for Co/sup 57/ sources are also reported. Calculations on the use of nuclear resonant absorption to measure gravitational fields and altitudes were made which indicates that this application is not promising. (D.L.C.)
Date: February 23, 1962
Creator: Ezop, J. J.
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
Fast Flux Test Facility. Design and Development Quality Assurance Requirements for the FFTF (open access)

Fast Flux Test Facility. Design and Development Quality Assurance Requirements for the FFTF

The document is presented to provide general management requirements for Pacific Northwest Laboratory (PNL) and contractor design and development quality assurance programs to assure the required quality level of the various items required for the FFTF. The document is applicable as imposed by the contract to FFTF contractors and subcontractors. The document is also applicable to PNL design and development activities related to the FFTF.
Date: October 23, 1968
Creator: Albert, W. G.
Object Type: Report
System: The UNT Digital Library
Vapor Containment in the Oak Ridge Research Reactor (open access)

Vapor Containment in the Oak Ridge Research Reactor

Containment of the ORR is attained by means of a ventilation system which is capable of exhausting air from the building at a rate sufficient to ensure that all leakage of air at ground level is into the building. The exhaust air is treated by scrubbing and filtration and is discharged from a large stack at a height and velocity sufficient to guarantee that meteorological dispersion will reduce the resulting concentration of radioactive material to an acceptable level. Factors involved in selection of this type of controlled containment are discussed. Original design and modifications are described. Performance is also discussed. (M.C.G.)
Date: August 23, 1962
Creator: Binford, F.T.
Object Type: Report
System: The UNT Digital Library
Calculation of Doppler Coefficient and Other Safety Parameters for a Large Fast Oxide Reactor (open access)

Calculation of Doppler Coefficient and Other Safety Parameters for a Large Fast Oxide Reactor

Several safety parameters are calculated for a large, fast, Na-cooled, oxide-fueled reactor. The Doppler coefficient is studied as regards its effect on the reactivity during a power excursion, and its dependence on the neutron spectrum, on the concentrations of U/sup 238/, Pu /sup 239/ , a nd Pu/sup 240/, on spatial temperature and power distributions, and on temperature. Other parameters studied include the Na temperature coefficient of reactivity, and the reactivity insertion caused by total Na loss; reactivity coefficients caused by thermal expansion of fuel and steel cladding; the excess operating reactivity; and the reactivity caused by a fuel slump. The effects of a Be reflector on neutron lifetimes are determined. The safety aspects are balanced against economic considerations. (T.F.H.)
Date: March 23, 1961
Creator: Greebler, P.; Hutchins, B. A. & Sueoka, J. R.
Object Type: Report
System: The UNT Digital Library
Problems Encountered During Four Years of ORR Operation (open access)

Problems Encountered During Four Years of ORR Operation

The over-all design and operation of ORR is reviewed in the light of four years of operating experience. Items discussed consist of the reactor components and instrumentation, reactor and pool cooling systems (including system cleanup), the emergency systems for electric power and reactor cooling, the waste-disposal systems (liquid, gaseous, and solid), and the building, itself. The ORR was the first of a class of reactors which combined the features of both the pool-reactor and tank-reactor types. Four years of operation indicated areas where problems of various degrees have developed. These problems are discussed. (auth)
Date: August 23, 1962
Creator: Tabor, W.H. & Costner, R.A. Jr.
Object Type: Report
System: The UNT Digital Library
OGRE-P1, A Monte Carlo Program for Computing Gamma-Ray Transmission Through Laminated Slabs (open access)

OGRE-P1, A Monte Carlo Program for Computing Gamma-Ray Transmission Through Laminated Slabs

A Monte Carlo IBM-7090 program (OGRE-P1) was written for calculation of the dose rate on one side of a slab owing to an isotropic, cosine, or collimated monoenergetic gamma radiation source on the other side of the slab. A maximum of 50 homogeneous regions are permitted. (auth)
Date: May 23, 1962
Creator: Trubey, K. K.; Penny, S. K. & Emmett, M. B.
Object Type: Report
System: The UNT Digital Library
Effect of Explosive Impacting on Uranium (open access)

Effect of Explosive Impacting on Uranium

Abstract: The tensile and yield strengths of both cast and wrought uranium discs were substantially increased by explosively impacting them at room temperature and at 375 deg F. However, the room-temperature impacting caused gross damage in the cast material and slight internal damage in the wrought material at the highest impacting pressures. Impacting at 375 deg F, which is just above the brittle-ductile transition temperature for uranium, was the most effective method for increasing the strengths with no damage to either the cast or wrought material. This impacted material retained some of its increased strength after a low temperature (425 deg C) vacuum anneal that greatly increased the elongation. A salt anneal caused a partial recrystallization in the impacted cast uranium. (auth).
Date: April 23, 1964
Creator: Burditt, R. B.; Carey, W. T. & Coughlen, C. P.
Object Type: Report
System: The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients (open access)

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Object Type: Report
System: The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps (open access)

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Object Type: Report
System: The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept (open access)

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept

Fifth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Object Type: Report
System: The UNT Digital Library
Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests (open access)

Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests

Report issued by the APDA over studies conducted on the requirements of reactors for fuel testing. As stated in the summary, "the purpose of this study is to determine the requirements for radiation space for fast reactor fuel testing and to determine the capability of existing Commission and private test and power reactors to meet these requirements" (p. 7). This report includes tables, and illustrations.
Date: February 23, 1963
Creator: Doyle, T. A.; Duffy, J. G.; Jens, W. H.; McHugh, W. E.; Page, E. M. & Warberg, H. S.
Object Type: Report
System: The UNT Digital Library
LONGITUDINAL RESISTIVE INSTABILITIES OF INTENSE COASTING BEAMS IN PARTICLE ACCELERATORS (open access)

LONGITUDINAL RESISTIVE INSTABILITIES OF INTENSE COASTING BEAMS IN PARTICLE ACCELERATORS

The longitudinal electromagnetic interaction of an intense coasting beam with itself, including the effect of a resistive vacuum tank, is investigated theoretically. It is shown that even in the range where the particle frequency is an increasing function of particle energy, the beam can be longitudinally unstable due to the resistivity of the vacuum tank walls. In the absence of frequency spread in the unperturbed beam the beam is shown to be always unstable against longitudinal bunching with a growth rate which depends upon (N/{sigma}){sup 1/2}, where N is the number of particles in the beam and {sigma} is the conductivity of the surface material. By means of the Vlasov equation, a criterion for stability of the beam is obtained; and shown in the limit of high-conductivity walls to involve the frequency spread in the unperturbed beam, the number of particles N, the beam energy, geometrical properties of the accelerator, but not the conductivity {sigma}. A numerical example is presented which indicates that certain observations of beam behavior in the MURA 40 MeV electron accelerator may be related to the phenomena investigated here.
Date: October 23, 1963
Creator: Neil, V. Kelvin & Sessler, Andrew M.
Object Type: Article
System: The UNT Digital Library
BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. March through05/1963 (open access)

BIO-ORGANIC CHEMISTRY QUARTERLY REPORT. March through05/1963

This report covers the following titles: (1) Fertility and litter size of normally ovulated and artificially ovulated mice; (2) Further studies on sterility produced in male mice by deuterium oxide; (3) Planarian disaggregation; (4) Uptake of organic compounds by planarians. II; (5) Effects of environmental complexity and training on acetylcholinesterase and cholinesterase activity in rat brain; (6) Effects of environmental complexity and training on brain chemistry and anatomy among mature rats; (7) Improvements in paper chromatographic techniques for labeled cell extracts; (8) measurement and adjustment of pH in small volumes of solutions; (9) Carbon-14 and Nitrogen-15 tracer studies of amino acid synthesis during photosynthesis by Chlorella Pyrenoidosa; (10) Photosynthesis of {sup 14}C-labeled protein from {sup 14}CO{sub 2} by Chlorella; (11) Further studies on carboxydismutase; (12) Electron microscopy of chlorophyll a crystals; (13) The possible role of chromanyl phosphates in oxidative and photosynthetic phosphorylation; (14) Oxidation-reductions of some coenzymes; (15) Preparation of some [{sup 14}C] labeled substances: glucose-6-phosphate, fructose-6-phosphate, 6-phosphogluconic acid, pyruvic acid, and succinic acid; (16) attempt to synthesize high molecular weight polynucleotides using Schramm's purely chemical method; and (17) Optical properties of some dye-polyanion complexes.
Date: July 23, 1963
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Subsonic capability of Pratt and Whitney turbojet power plants (open access)

Subsonic capability of Pratt and Whitney turbojet power plants

None
Date: March 23, 1960
Creator: Nicoll, H. E.
Object Type: Report
System: The UNT Digital Library
Supersonic capability of Pratt and Whitney turbojet power plants (open access)

Supersonic capability of Pratt and Whitney turbojet power plants

None
Date: March 23, 1960
Creator: Thome, P.G.
Object Type: Report
System: The UNT Digital Library
Power plant weight status. 140E1 (ACT) (open access)

Power plant weight status. 140E1 (ACT)

None
Date: March 23, 1961
Creator: Phelps, E.
Object Type: Report
System: The UNT Digital Library
A STUDY OF RESONANCES OF THE Z-7r SYSTEM (open access)

A STUDY OF RESONANCES OF THE Z-7r SYSTEM

Recently a T = 1 resonance in the {Lambda}-{pi} system called Y{sub 1} has been observed with a mass of 1385 MeV. Two types of resonances have been predicted that might relate this observation to other elementary-particle interactions: (1) P 3/2 resonances in the {Lambda}-{pi} and {Sigma}-{pi} systems predicted by global symmetry, corresponding to the (3,2/ 3/2) resonance of the {pi}-N system, (2) a spin-1/2 Y-{pi} resonance resulting from a bound state in the {bar K}-N system. The position and the width of the observed Y{sub 1} resonance agree with both theories, but since the spin and parity have not yet been determined, they cannot distinguish between the two theoretical interpretations.
Date: May 23, 1961
Creator: Alston, M.H.; Alvarez, L.W.; Eberhard, P.; Good, M.L.; Graziano,W.; Ticho, H.K. et al.
Object Type: Report
System: The UNT Digital Library