Neutron Diffraction Studies at the Puerto Rico Nuclear Center (open access)

Neutron Diffraction Studies at the Puerto Rico Nuclear Center

A neutron diffraction program was initiated recently at the Puerto Rico Nuclear Center. The two double crystal spectrometers in use were assembled with the aid of staff members of the Brookhaven National Laboratory. The first research problem to be completed was a single crystal structure analysis of CaWO4. Choosing the origin at the 4(a) tungsten site in the tetragonal I41/a cell. the 16(f) oxygen parameters were found to be as follows: x=0.2413 ± 0.0005, y=0.1511 ± 0.0006, z=0.0861 ± 0.0001. Anisotropic temperature parameters were also determined for all atoms in the least squares analysis of the structure. The magnetic structure of CuSO4 has been determined in a continuation of a study started at Brookhaven in collaboration with Dr. P.J. Brown. Using the Wollan-Koehler-Bertaut notation, the antiferromagnetic spin ordering mode in the orthorhombic Pbnm cell is Ax, with the spin axis parallel to a. A moment of approximately 1 μB was found for the Cu2_ ion. The crystal structure of BaNiO2 was re-examined in a neutron powder diffraction study, and it was found that the earlier x-ray study of Lander is essentially correct. An alternative oxygen arrangement, for which x-rays would not have been very sensitive, had been suspected. BaNiO2 was …
Date: October 15, 1963
Creator: Almodovar, I; Bielen, H. J. & Frazer, B. C.
Object Type: Report
System: The UNT Digital Library
Fabrication of Uranium Wire (open access)

Fabrication of Uranium Wire

From abstract: "The present report describes experimental work performed to establish a procedure for the production of uranium metal wire. In all cases, the size of the initial rod was 1/2 inch diameter. Three materials were used: hot extruded tuballoy rod, high purity cast tuballoy rod, and cast U-235 rod."
Date: October 25, 1949
Creator: Anderson, R. E.; Taub, J. M. & Doll, D. T.
Object Type: Report
System: The UNT Digital Library
Radiocarbon from Pile Graphite; Chemical Methods for its Concentration (open access)

Radiocarbon from Pile Graphite; Chemical Methods for its Concentration

Abstract. Samples of pile graphite, irradiated in a test-hole at Hanford for 15 months, have been assayed for radioactive C14, yielding 0.38 ± 0.04 microcuries per gram. At this level of activity, the pile graphite contains very valuable amounts of C14. The relation between the above assay and the probable average assay of pile graphite is discussed, and it is concluded that the latter is almost certainly above 0.3 uc/ gram. Controlled oxidation of this graphite, either with oxygen at ~ 750°C, or with chromic acid "cleaning solution" at room temperature, yields early fractions which are highly enriched in C14. Concentrations of 5-fold with oxygen, and 50-fold with CRO{sub3}, have been observed. The relation between the observed enrichment and the Wigner effect is discussed, and a mechanism accounting for the observations put forward. According to this, about 25% of the stable carbon atoms in the lattice have been displaced by Wigner effect, a large fraction of which have healed the migrating to crystal edges. All the C14 atoms have been displaced, and the same fraction of these migrate to the edges. The enrichment then results from surface oxidation, in the oxygen case. Predictions are made on the basis of this …
Date: October 10, 1946
Creator: Arnold, James R. & Libby, Willard F.
Object Type: Report
System: The UNT Digital Library
Instructions for the Operation of an ORACLE Code for a Monte Carlo Solution of the Transport Problem for Gamma Rays Incident Upon a Slab (open access)

Instructions for the Operation of an ORACLE Code for a Monte Carlo Solution of the Transport Problem for Gamma Rays Incident Upon a Slab

A program has been coded for the ORACLE which will solve, using Monte Carlo technique, the transport problem for monodirectional, monoenergetic gamma radiation incident at an angle Θ, upon an infinite laminated slab of finite thickness. Each of the laminations (or regions) is itself an infinite, homogeneous slab of finite thickness. The code is designed to give estimates of energy deposition, energy flux, tissue dose rate, reflected and transmitted energy current, and the angular and energy distribution of the reflected and transmitted energy current. All the answers except for energy deposition and reflected and transmitted energy current are optional.
Date: October 26, 1960
Creator: Aulender, S. & Trubey, D. K.
Object Type: Report
System: The UNT Digital Library
Analysis  of Uranium-Manganese Alloys (open access)

Analysis of Uranium-Manganese Alloys

Introduction. the conventional procedures of analysis for uranium and manganese can be employed in the analysis of alloys of these metals. The alloys are reacted with perchloric acid and hydrogen peroxide, fumed to remove any chloride ions, diluted to volume and aliquots analyzed by redoximetry.
Date: October 5, 1945
Creator: Ayers, A. S.
Object Type: Report
System: The UNT Digital Library
Precipitation of Thorium Oxalate from Nitric Acid Solutions (open access)

Precipitation of Thorium Oxalate from Nitric Acid Solutions

Introduction. It has been known for a long time that thorium is precipitated by oxalic acid in acid solutions, but a survey of the literature showed no study of the limits of the acidity and oxalic acid excess which yield quantitative results. V. I. Spitzin reports on the solubility of thorium oxalate in varying concentrations of several acids, but the effect of an excess oxalic acid is not included. Since solutions are sometimes presented for analysis that contain more than the recommended two per cent mineral acid, it would be advantageous to be able to quantitatively remove the thorium without otherwise altering the solutions. This was especially of interest in solutions containing bismuth, since it was hoped that some amounts of thorium could be precipitated in nitric acid solutions containing large quantities of bismuth. In removing the bismuth, first by a bismuth oxychloride precipitation, thee is every opportunity for carrying of the thorium.
Date: October 5, 1945
Creator: Ayers, A. S.
Object Type: Report
System: The UNT Digital Library
Enclosure Pressure Calculation Method (open access)

Enclosure Pressure Calculation Method

A method of determining enclosure pressure in the event of a reactor rupture is presented and a sample calculation is shown. This method was used in calculating the design pressure of the Dresden Nuclear Power Station enclosure.
Date: October 6, 1956
Creator: Bailey, J. A.
Object Type: Report
System: The UNT Digital Library
Transistorized Linear Pulse Amplifiers (open access)

Transistorized Linear Pulse Amplifiers

The basic investigation of transistor feedback amplifiers has proven mathematically simple and of great practical value. The behavior of single-stage common-emitter amplifiers is described and provides a building block with which cascaded feedback amplifiers can be analyzed and designed. From the results of this analysis the conditions for minimum drift for cascaded single-stages and cascaded loops have been derived.
Date: October 27, 1958
Creator: Baker, Stanley C.
Object Type: Report
System: The UNT Digital Library
Total Cross Sections for K Mesons and π Mesons on Protons and Deuterons between 2.5 and 6 BeV/c (open access)

Total Cross Sections for K Mesons and π Mesons on Protons and Deuterons between 2.5 and 6 BeV/c

Recent measurements of the pion-proton total cross section, taken with small statistical errors, have shown the existence of two new maxima in the momentum range between 2 and 3 BeV/c. Measurements of comparable statistical accuracy, covering the momentum range from 2.5 to 8 BeV/c are reported in the present paper. In addition to the total cross sections for π± mesons on protons, their total cross sections on deuterons have also been determined. Some data were also taken on the total cross sections for K+ mesons on protons and deuterons and for K- mesons on protons.
Date: October 1, 1963
Creator: Baker, W. F.; Jenkins, E. W.; Kycia, T. F.; Phillips, R. H.; Read, A. L.; Riley, K. F. et al.
Object Type: Report
System: The UNT Digital Library
Interactions of High Energy Antiprotons in Hydrogen (open access)

Interactions of High Energy Antiprotons in Hydrogen

In the fall of 1961 an extensive program of investigation of high energy p-p interactions was begun at the Brookhaven AGS. The BNL 20" liquid hydrogen bubble chamber and an electrostatically separated beam were used to obtain a total (to date) of 300,000 exposure with about 15 antiprotons per pulse. The exposures were made at antiproton momenta of 3.25 Bev/c and 3.69 Bev/c in the laboratory. Approximately 80% of the exposures were made 3.69 Bev/c antiprotons. A wide variety of reactions occur in these collisions. Some of these such as elastic scattering, pion production, and associated production of hyperons and K-mesons have analogues in p-p collisions. The similarities and differences between the p-p and p-p results can usually be understood in a qualitative way and in some cases quantitative comparison with theory has been possible. The annihilation reactions leading to final states containing pions alone or pions with K-mesons are unique to the nucleon-antinucleon system as are the reactions in which a hyperon, anti-hyperon pair is produced. In the following, we report the principal characteristics of proton-antiproton reactions. Although the scope of this paper is comprehensive it is not a definitive report of the experiment as much of the work …
Date: October 15, 1963
Creator: Baltay, C.; Ferbel, T.; Sandweiss, J.; Taft, H. D.; Culwick, B. B.; Fowler, W. B. et al.
Object Type: Report
System: The UNT Digital Library
Adenosinetriphosphate Cleavage During the G-Actin to F-Actin Transformation and the Binding of Adenosinetriphosphate to F-Actin (open access)

Adenosinetriphosphate Cleavage During the G-Actin to F-Actin Transformation and the Binding of Adenosinetriphosphate to F-Actin

Since the discovery of the Straub and Feuer as well as Laki et al. that ATP bound to G-actin is transformed to ADP and inorganic phosphate during polymerization of actin (1, 2), it has become increasingly clear that the chemical changes in the nucleotide are related to the change in the physical state of the protein. Barany, Biro, Molnar and Straub have shown that highly purified actin preparation free of any enzyme which would use ATP, ADP or AMP as a substrate still catalyze the breakdown of ATP (3) thus supporting the original idea that the ATP to ADP transformation is related to the globular to fibrous transformation of the actin protein itself. Mommaerts was the first to show that the ADP formed during polymerization remains bound to F-actin and Ulbrecht et al. while extending Mommaert's finding on exhaustively purified actin preparations have shown that the P1 formed during polymerization is not bound to F-actin. The stoichiometry of the splitting and the tightness of binding of the ADP lead inevitably to questions in regard to the position of bond breaking during the hydrolysis and to the nature of the forces involved in the tight binding of ADP to F-actin. To …
Date: October 15, 1963
Creator: Barany, M.; Koshland, D. E., Jr.; Springhorn, S. S.; Finkleman, F. & Theratil-Anthony, T.
Object Type: Report
System: The UNT Digital Library
The Activation of Low-Reactivity Uranium Dioxide Particles (open access)

The Activation of Low-Reactivity Uranium Dioxide Particles

A detailed study of the activation of low-reactivity UO2 particles toward HF by successive oxidation and reduction was carried out. The effect of repeated successive oxidation and reduction on the reactivity of the UO2 source material toward HF was evaluated by hydrofluorination.
Date: October 1955
Creator: Bard, R. J.; Bunker, D. L.; Greenough, R. C. & Kalmus, E. H.
Object Type: Report
System: The UNT Digital Library
Direct Current Electromagnetic Pumps (open access)

Direct Current Electromagnetic Pumps

Abstract: "A number of direct current conduction type electromagnetic pumps for liquid metals were constructed. Pumping capacities of over 400 gpm and efficiencies of over 50 percent were obtained. NaK alloy at temperatures up to 400 C was used in the test. The large currents required were obtained from rectifiers or from a homopolar generator constructed for the purpose."
Date: October 25, 1949
Creator: Barnes, A. H.; Smith, F. A. & Whitham, G. K.
Object Type: Report
System: The UNT Digital Library
Pile Neutron Production Field Curves Calculated Using the UCRL Differential Analyzer (open access)

Pile Neutron Production Field Curves Calculated Using the UCRL Differential Analyzer

A set of 69 pile yield curves for the production of plutonium, americium, and curium isotopes in a neutron flux of 5 x 10<sup>14 cm<sup>-2 sec<sup>-1 is given. The differential analyzer of the University of California Radiation Laboratory was used in obtaining the curves. The curves are given also on log-log plots for comparison.
Date: October 30, 1953
Creator: Barrett, R. J.; Killeen, John, 1925-; Rasmussen, J. O. & Thompson, Stanley Gerald, 1912-1976
Object Type: Report
System: The UNT Digital Library
Electrical Design Standards and Graphical Symbols (open access)

Electrical Design Standards and Graphical Symbols

This manual represents the recommendations of the Instrumentation and Controls Division committee on Electrical and Electronic Symbols and Drawing that have been issued to date, and supersedes the previously issued ORNL Electrical Symbols List and CF-58-12-141, Electrical and Electronic Drawing Standards for Wiring and Device Coding and Applications.
Date: October 1960
Creator: Bates, A.E.G; Bowelle, M.M.; Horton, J. L.; Moore, R. L.; Hyland, R. F. & Brashear, C.
Object Type: Report
System: The UNT Digital Library
On the Crystal Chemistry of Salt Hydrates, II. A Neutron Diffraction Study of MgSO4·4H2O (open access)

On the Crystal Chemistry of Salt Hydrates, II. A Neutron Diffraction Study of MgSO4·4H2O

The crystal structure of MgSO4·4H2O has been refined using single crystal neutron diffraction data for the three main zones. The hydrogen positions which were found are essentially those which have been deduced from X-ray data in an earlier investigation.The mean value of the O-H bond lengths is 0.97Å. The O-H-O bonds are bent considerably. One hydrogen atom does not participate in hydrogen bonding, as can be concluded from the geometry of its surroundings and its thermal motion.
Date: October 15, 1963
Creator: Baur, Werner H.
Object Type: Report
System: The UNT Digital Library
On the Crystal Chemistry of Salt Hydrates, III. The Determination of the Crystal Structure of FeSO4·7H2O (Melanterite)* (open access)

On the Crystal Chemistry of Salt Hydrates, III. The Determination of the Crystal Structure of FeSO4·7H2O (Melanterite)*

Monoclinic FeSO4·7H2O is the stable solid phase between -1.82° and 56.6° C in contact with a saturated water solution of FeSO4. It occurs in nature as an oxidation product of Fe-containing sulfides an is called melanterite. FeSO4·7H2O belongs to a series of compounds Me2+SO4·nH2O, where Mn2+ is a cation with an approximate ionic radius of 0.7Å. The 1-, 4- and 5-hydrates are known to crystalize each in only one form, whereas the hexa- and the heptahydrates occur both in two different forms. The crystal structure of the tetragonal NiSO4·6H2O; Zalkin, Ruben and Templeton reported the structure of the monoclinic CoSO·6H2O. Of the structure of the heptahydrates but one was described: the orthorhombic form of NiSO4·7H2O. No details were known about one of the monoclinic heptahydrates, though Leonhardt and Ness published the cell constants and the space group of FeSO4·7H2O.. In addition they stated essentially correct positional parameters for the sulfur atom and gave the correct positions of the iron atoms. The present investigation has been undertaken as part of an extensive study of salt hydrates. A preliminary account has been published before.
Date: October 15, 1963
Creator: Baur, Werner H.
Object Type: Report
System: The UNT Digital Library
A Method for Rolling Uranium Foil (open access)

A Method for Rolling Uranium Foil

"This report gives briefly a rather simple method for fabricating foils from uranium buttons. Two log sheets one of a U-238 run and one of a U-255 run are given."
Date: October 21, 1947
Creator: Bernard, George L., (Jr.)
Object Type: Report
System: The UNT Digital Library
Basic Gamma-Ray Data for ART Heat Deposition Calculations (open access)

Basic Gamma-Ray Data for ART Heat Deposition Calculations

In order that fairly accurate thermal stress calculations can be made on the ART, it is necessary to have a reasonable picture of the temperature distribution in the reactor. To get the temperature distributions, and to determine cooling requirements in various parts of the reactor, one must know the heat deposition rates due to alpha particles, beta rays, gamma rays, and neutrons in all parts of the reactor. The present report contains only the basic physical data necessary to determine the heat deposition rates due to gamma rays. Neutron fluxes in the core and reflector regions of the ART are to be obtained from two-dimensional multigroup calculations (performed by the Curtiss-Wright Corporation). These fluxes, in conjunction with the neutron absorption cross sections, determine the neutron capture and inelastic scattering rates in the core and in the reflector. The data in this report permit the calculation of the number of gamma rays originating at various energies at every point in the core and reflector.
Date: October 3, 1956
Creator: Bertini, H. W.; Copenhaver, C. M.; Perry, A. M. & Stevenson, R. B.
Object Type: Report
System: The UNT Digital Library
The Oak Ridge National Laboratory Research Reactor Safeguard Report (open access)

The Oak Ridge National Laboratory Research Reactor Safeguard Report

The proposed ORNL Research Reactor is designed to serve as a general purpose research tool delivering a maximum thermal flux of 8x10^13 n/cm2-sec at the initial power level of five megawatts. Operation at power levels up to ten megawatts is proposed for such items as sufficient cooling capacity is available to handle the increased heat load. The reactor will use MTR-type fuel elements and beryllium reflector pieces in a 7 x 9 grid with moderation and cooling provided by forced circulation of demineralized water. The reactor tanks are submerged in a barytes concrete pool, filled with water, which serves as a biological shield. Experimental facilities include two 18" diameter "Engineering Test Facilities" and six 6" diameter beam holes. In addition, access to the core is available through the water of the pool. The result on the surrounding population of release to the atmosphere of a large fraction of the radioactive material in the core has been computed by two methods. It is shown that under certain conditions off-area personnel could be subjected to greater than the maximum permissible exposure. An analysis of the maximum hazard caused by the release of the entire contents of the core to the local watershed …
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J. P.
Object Type: Report
System: The UNT Digital Library
The Oak Ridge National Laboratory Research Reactor Safeguard Report (open access)

The Oak Ridge National Laboratory Research Reactor Safeguard Report

This memorandum sets forth a recommended uniform basis for designing the ORN shield.This includes design values for power level and emergent radiation, standards values for various material properties, and basic radiation intensities.
Date: October 7, 1954
Creator: Binford, F. T.; Cole, T. E. & Gill, J.P.
Object Type: Report
System: The UNT Digital Library
Accelerator Development Department Internal Report (open access)

Accelerator Development Department Internal Report

In this report we present solutions of the design problem in which a system of quadruple lenses is required to carry a particle beam from given focal lines in the x and y planes to other given focal lines. Particular attention will be given to the case of the anastigmatic lens system which takes a beam from one focal point to another focal point. Since the general problem is almost impossibly complicated a simplification is introduced by breaking the lens system into two parts. The first part of the lens system is required to bring the initial beam to the state where it is parallel to the z axis in both planes. The second part carries the initially parallel beam to the required final condition. Each part will involve two quadrupoles so that the complete system will consist of four quadruples; usually, however, the field gradients in the second and third quadrupoles can be made identical so that those quadrupoles can be combined into one and the system becomes a three quadrupole system. The configuration of the lens element will be as shown in the figures below. These figures indicate also the general character of the beam path in the …
Date: October 2, 1958
Creator: Blewett, J. P.
Object Type: Report
System: The UNT Digital Library
Aqueous Uranium Slurry Studies (open access)

Aqueous Uranium Slurry Studies

A summary of the laboratory development program on aqueous uranium slurry fuels for the Homogenous Reactor Project during the period April 1951 through March 1953 is presented. These investigations were devoted primarily to a study of the uranium oxides in aqueous suspensions. It was concluded that U(VI) was most likely to be the stable valence state in such slurry fuels and it was shown that β-UO3·H2O platelet crystals were the stable modification at 250°C. Very pure slurries of β-UO3·H2O platelets, uranium concentration of 250g/liter and average particle size of about 10 μ, had favorable settling rates and could be easily redispersed. Their viscosity and corrosion rate in stainless steel were comparable with those in water. Exposure of these slurries to pile radiation disclosed that radiolytic hydrogen and oxygen gas pressure comparable in magnitude to those of uncatalyzed uranyl sulfate solutions could be expected. Fission products in the irradiated slurries were predominantly associated with the solids. Radiation also tended to promote caking of these solids on the walls of the radiation bombs. Uranyl phosphate and the magnesium uranates were briefly investigated as alternate system but were not found satisfactory. The program was discontinued before the feasibility of uranium slurries for reactor …
Date: October 20, 1955
Creator: Blomeke, J. O.; Bamberg, J. L.; Blomeke, J. O.; Bruce, F. R.; Fulmer, J. M.; McBride, J. P. et al.
Object Type: Report
System: The UNT Digital Library
Unit Operations Section Monthly Progress Report July 1959 (open access)

Unit Operations Section Monthly Progress Report July 1959

A Lucite model of a multi-stage countercurrent hydroclone solvent extraction apparatus has been constructed and tested with Amsco-water. The diffusivity of Cs 134 tracer in aqueous chloride solution was measured to check the performance of the capillary diffusivity measuring system. The experimental data from four Druhm runs showed that 1/8in. thick graphite liners are usable for reactor temperatures above the boiling point of sodium.
Date: October 9, 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