A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations (open access)

A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations

An IBM 1620 program is described that calculates the Bragg angles for cubic, hexagonal, and tetragonal crystal systems for use with powder x-ray diffraction techniques. Allowance is made for absent reflections in the case of face- and body-centered cubic and close-packed hexagonal materials.
Date: April 1963
Creator: Walker, D. G.
System: The UNT Digital Library
A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method (open access)

A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method

An I.B.M. 1620 programme is described which calculates refined lattice parameters from X-ray diffraction data according to Hess' Method. The programme may be used for cubic, hexagonal, and tetragonal systems and three systematic error functions are included. The output includes the refined parameters their stand errors, and the misfit of the data at each experimental point.
Date: April 1963
Creator: Walker, D. G.
System: The UNT Digital Library
The A.A.E.C. Atmospheric Pressure Heat Transfer Rigs (open access)

The A.A.E.C. Atmospheric Pressure Heat Transfer Rigs

This technical report describes two atmospheric pressure rigs with associated equipment designed for investigating heat transfer and friction characteristics of different type of "roughened" surfaces to develop suitable surfaces for an H.T.G.C.R. fuel element. Operating details are given together with techniques used to measure heat transfer and friction on a surface assembly incorporating selected "roughened" surfaces. Methods for calculating Stanton numbers, friction factors, and Reynolds numbers for such an assembly are included.
Date: 1961
Creator: Lawther, K. R. & Draycott, A.
System: The UNT Digital Library
Adaptation of the Siemens Diffractometer for Precision Lattice Parameter Determinations of Single Crystals (open access)

Adaptation of the Siemens Diffractometer for Precision Lattice Parameter Determinations of Single Crystals

Modifications to the A.A.E.C.'s Siemens Diffractometer are described which enable precision lattice parameter determinations on single crystals. Analysis of the errors and consideration of results suggest that accuracies of about 1--2 parts in 10/sup 5/ are obtained on small beryllium oxide crystals. Details of alignment and measurement procedure are included.
Date: August 1963
Creator: Mayer, R. M. & Walker, D. G.
System: The UNT Digital Library
An Analysis of Instrumental Errors Affecting the Performance of a Schultz-Type Texture Goniometer (open access)

An Analysis of Instrumental Errors Affecting the Performance of a Schultz-Type Texture Goniometer

The performance of a Schultz-type texture goniometer is shown to be adversely affected by a number of experimental errors all of which result in defocusing of the diffracted beam. Those errors result from the tilting of the specimen, from lack of precision in positioning it and from its absorption coefficient. An experimental procedure is outlined which minimized these errors and results in optimum performance of the instrument.
Date: 1962
Creator: Kelly, J. W.
System: The UNT Digital Library
An Apparatus for Differential Thermal Analysis and its Use in the Investigation of Some Beryllium Compounds (open access)

An Apparatus for Differential Thermal Analysis and its Use in the Investigation of Some Beryllium Compounds

An apparatus for differential thermal analysis of active or toxic materials is described. The technique is superior to thermogravimetric analysis. Analysis of the dehydration of beryllium sulphate shows that the process takes place in three stages. Some applications are given for a modified apparatus for quantitative work.
Date: 1962
Creator: O'Connor, D. J.
System: The UNT Digital Library
An Apparatus for Dissolving Irradiated Fuel Specimens and Accurately Sampling the Solution (open access)

An Apparatus for Dissolving Irradiated Fuel Specimens and Accurately Sampling the Solution

Details are given of an apparatus used to dissolve irradiated ceramic, metallic, and carbide fuel specimens, to dilute the dissolver solutions accurate to a known volume, and to take aliquots with a specially adapted automatic burette. Procedures for its use are given.
Date: September 1962
Creator: Coady, John Robert & arrell, M. S. (Michael S.)
System: The UNT Digital Library
The Aqueous Coordination Chemistry of Beryllium and its Relation to Fuel Processing - a Literature Survey (open access)

The Aqueous Coordination Chemistry of Beryllium and its Relation to Fuel Processing - a Literature Survey

A survey of the aqueous coordination chemistry of beryllium is given. The possible use of coordination chemistry in the separation of beryllium from fission products is discussed, outlining methods for separation processes.
Date: November 1962
Creator: Aggett, J. (John)
System: The UNT Digital Library
Automatic Scaler A.A.E.C. Type 2A -- Service Manual (open access)

Automatic Scaler A.A.E.C. Type 2A -- Service Manual

This manual is intended to give operating and maintenance information for the range of counting equipment in use by the A.A.E.C. at Lucas Heights, designation of Scaler Type 2A. This equipment has been designed in the General Physics Section of the A.A.E.C. General Nucleonics Division. The equipment was built by an Australian manufacturer (Siemens Nucleonics).
Date: July 1963
Creator: Fraser, H. J. & Waldron, C.
System: The UNT Digital Library
Automatic Solution of Optimum Design Problems on a Digital Computer (open access)

Automatic Solution of Optimum Design Problems on a Digital Computer

A description is given of a method suitable for the automatic solution of certain optimum design problems on a digital computer for cases where the number of constraints imposed on the design is not greater than the number of design variables. The problem is transformed to one requiring the minimization or maximization of an unconstrained function, for which a gradient method is used.
Date: March 1962
Creator: Lawrence, B. R.
System: The UNT Digital Library
Axial Temperature Distributions in Concentric Cooling Channels Surrounding a Heat Generating Source (open access)

Axial Temperature Distributions in Concentric Cooling Channels Surrounding a Heat Generating Source

A set of simultaneous differential equations is established to describe the temperature distribution for coolant flow in three concentric channels separated by walls of finite thermal conductivity and surrounding a cylindrical heat source. The solution of this set of differential equations is dependent on the heat source function Q(z) which must be known or specified. An assumed function Q(z) constant is taken as being a representative case and the resultant solutions are applied to several geometric arrangements. The system of three channel flow reduces to two channel flow when there is zero heat flow across the outer intermediate wall. This condition may arise if the wall is a perfect insulator, or if the flow in the third channel is zero. For the former case the temperature in the third channel is constant over its length, and in the second the stationary coolant assumes the temperature of the coolant in the middle channel. From the set of differential equations established for two channel flow, treatment similar to that used for three channel flow is adopted and the resultant solutions are applied to several geometric arrangements. Brief mention is made of single channel flow. By assuming that the heat sources is zero …
Date: 1962
Creator: Carr, F. H.
System: The UNT Digital Library
A Basis for the Computation of the Energy Dependence of the Neutron Flux and Slowing Down Density in a Bare Reactor (open access)

A Basis for the Computation of the Energy Dependence of the Neutron Flux and Slowing Down Density in a Bare Reactor

A method is described for the computation of the energy dependence of the neutron flux and slowing down density in a bare reactor to form the basis of a 7090 Fortran computer program for survey studies of power reactors. Allowance is made for resonance absorption and resonance fission, neutron thermalisation, fast neutron reactions including (n, 2n) and (n, n), and anisotropic elastic scattering.
Date: September 1963
Creator: Lawrence, B. R.
System: The UNT Digital Library
Binary and Ternary Systems Involving Beryllium Oxide - a Literature Survey (open access)

Binary and Ternary Systems Involving Beryllium Oxide - a Literature Survey

Data relating to the binary and ternary systems involving beryllium oxide are presented . The survey deals with all available literature up to December 1962.
Date: June 1963
Creator: Kairaitis, D.
System: The UNT Digital Library
The Calculation of Crystal and Counter Settings for the Collection of Crystallographic Data with a Counter-Diffractometer in the Equatorial Plane (open access)

The Calculation of Crystal and Counter Settings for the Collection of Crystallographic Data with a Counter-Diffractometer in the Equatorial Plane

Formulas are developed for the angle between any two vectors lying in a plane through the origin of reciprocal space. The application of these formulas for computing the counter and crystal angles for the collection of data with a counter-- diffractometer in the equatorial plane is developed, and a suitable computer program, written in FORTRAN without format suitable for an IBM 1620 computer, is described.
Date: January 1963
Creator: ryor, A. W. (Arthur William), 1928- & Sabine, T. M.
System: The UNT Digital Library
Calculation of Reactivity Changes in HIFAR Due to Fuel and Poison Changes (open access)

Calculation of Reactivity Changes in HIFAR Due to Fuel and Poison Changes

Empirical methods are given for calculating reactivity changes in HIFAR with changes in fuel loading, poison concentration, and temperature variations. The procedures are derived from the analysis of typical operating programs, reinforced by analogue computer analysis of variation of the important fission product poisons Xenon 135 and Samarium 149.
Date: January 1962
Creator: McKenzie , C. D. & Connolly , J. W.
System: The UNT Digital Library
A Comparative Study of Two Grades of BeO (open access)

A Comparative Study of Two Grades of BeO

Pechiney and Brush UOX BeO differ markedly in fabrication behaviour, only Brush UOX being readily sinterable. A comparative study of the two powders has shown few outstanding differences in powder properties. Both are of high purity but contain free and combined moisture to the extent of about 1.5 per cent. Pechiney BeO has a larger mean crystallite size (0.2 — 0.3μ) than Brush UOX (0.1 — 0.15μ) and a larger range of crystallite size, and both contain a small proportion of crystallites of size 1μ. and larger. The tap density of UOX is much lower than that of Pechiney, and its surface area is higher by a factor of two, UOX BeO can be hot—pressed or cold—pressed and sintered to high densities at temperatures of 1400º and 1500ºC respectively, which are approximately 300ºC lower than those required for Pechiney. Grain size of fabricated material increases with fabrication temperature in both grades, and at the same temperatures is larger for UOX than Pechiney. However, at comparable densities grain sizes are also comparable for the two materials, The bend strength at room temperature of hot—pressed Pechiney BeO reaches a maximum of approximately 30,000 p.s.i. when pressed at 1750ºC. Above this temperature the …
Date: November 1961
Creator: Reeve, Keith Desmond, 1928- & Ramm, E. J.
System: The UNT Digital Library
Cost Estimation for Nuclear Reprocessing Plants : a Comparison of Methods (open access)

Cost Estimation for Nuclear Reprocessing Plants : a Comparison of Methods

A comparison of methods of capital cost estimation used for nuclear fuel reprocessing plants shows that, because of the special nature and complexity of such plants, cost estimation methods for conventional chemical plants involving the use of cost factors are not applicable and will give low estimates. Cost factors which are available from other countries where reprocessing plants are installed should be used with caution since those factors apply only for the particular design philosophy used and pertain to industrial conditions which are different in this county. Capital cost estimation methods involving direct take-offs from detailed design drawings are necessary to obtain reliable estimates. The methods of estimating operating costs for nuclear reprocessing and conventional chemical plants are similar.
Date: March 1962
Creator: Alfredson, Peter George & Cairns, R. C.
System: The UNT Digital Library
A Cryostat for Temperature Control in the Range from Ambient to - 150 degrees C (open access)

A Cryostat for Temperature Control in the Range from Ambient to - 150 degrees C

This note describes a simple cryostatic device, which, by utilizing the latent heat of vaporization of liquid nitrogen, enables accurate control of temperature between ambient and - 150 degrees C. The advantages of this cryostat over other models known are simplicity of design and operation, ability to operate accurately from ambient to - 150 degrees C, economy, and large working space.
Date: April 1963
Creator: Roman, D.
System: The UNT Digital Library
Design of Concentric Tubular Reactor Fuel Elements for Uniform Coolant Conditions (open access)

Design of Concentric Tubular Reactor Fuel Elements for Uniform Coolant Conditions

Concentric tubular reactor fuel element geometries to give equal coolant outlet temperatures are presented. Oscillations from tube to tube in thickness and temperatures generally occur but it is possible to eliminate them by choice of the centre element. This may be a fuel rod or a non-heat—producing rod with or without a surrounding annulus of fuel. The geometries and temperatures are dependent on the voidage and on a non-dimensional parameter equivalent to a Biot number based on the channel equivalent diameter.
Date: June 1962
Creator: Binns, Ian M.
System: The UNT Digital Library
Determination of Beryllium, Thorium, and Uranium in Sulphuric - Phosphoric Acid Mixtures (open access)

Determination of Beryllium, Thorium, and Uranium in Sulphuric - Phosphoric Acid Mixtures

Methods are described for the determination of traces of Be, Th, and U in concentrated sulfuric-phosphoric acid mixtures. When the Be concentration is sufficiently high, the chrome azurol S spectrophotometric method may be applied directly, and a small correction made for phosphate interference. At lower concentrations Be should be first separated by an acetylacetone extraction. Th must be separated from sulfate and phosphate before the thoronol spectrophotometric method can be used. This is achieved by precipitating Th as the fluoride, using Y carrier. U may be determined spectrophotometrically with arsonazo after separating Be, Th, suIfate, phosphate, and other impurities by anion-exchange from hydrochloric acid solution. In an alternative procedure, U is reduced to the tetravalent state and precipitated with Th as the fluoride, again using Y carrier. The determination is then completed by a-c polarography.
Date: September 1962
Creator: Florence, T. M. & Shirvington, P. J.
System: The UNT Digital Library
Determination of Stability Constants in Stepwise Complex Formation (open access)

Determination of Stability Constants in Stepwise Complex Formation

It has been shown by studying the possibilities for determining the constants in stepwise complex formation by the interaction of hydrolyzed metal ions and ligands, that in a vast number of cases the direct measurements of metal ion and ligand activities ae necessary. Complete formulae for calculation are given and the conditions which allow some simplifications are established.
Date: 1961
Creator: Komar, N. P. & de Bruin, H. J.
System: The UNT Digital Library
Determination of the Formation Constant of Indiumacetylacetonate by an Extraction Method (open access)

Determination of the Formation Constant of Indiumacetylacetonate by an Extraction Method

1. The solubility of acetylacetone has been determined in an acetate buffer solution of ionic strength C.1 in relation to pH and temperature. 2. The distribution coefficients of acetylacetone have been determined between chloroform, carbon tetrachloride, benzene and an acetate buffer solution in relation to acetylacetone concentration and pH. 3. The relationship has been established between the rate at which indium acetylacetonate reaches partition equilibrium and the pH, initial acetylacetone concentration in the organic phase, and the different organic solvents. 4. The extent of the extraction of indiumacetylacetonate has been determined for three organic solvents at two acetylacetone concentrations in relation of pH. The independence of the degree of extraction from indium concentration was established in the region between 10(-4) to 10(-6) M. 5. 5. The indium acetylacetone compound was obtained by extraction from organic solvents. 6. The stability constants were calculated by two different methods for the uncharged complex and intermediate complexes; also the constants for the various steps of the dissociation of indiumacetylacetonate.
Date: 1959
Creator: Rudenko, N. P. (Nikolaĭ Petrovich); Stary, I. & de Bruin, H. J.
System: The UNT Digital Library
Determination of the Stability Constants of Salicylato-Beryllium Complexes by a Distribution Method (open access)

Determination of the Stability Constants of Salicylato-Beryllium Complexes by a Distribution Method

An investigation of the solvent extraction behavior of salicylato- beryllium complexes is reported. A simplified method for calculating the stability constants has been developed. The values obtained are beta /sub 1/ = 4.0 x 10/sup 12/ and beta /sub 2/ = 4 3 x 10/sup 22/ in 0.15 M sodium perchlorate. (auth)
Date: November 1, 1961
Creator: Szego, L. E.
System: The UNT Digital Library
A Differential Equation from the Theory of Neutron Thermalisation (open access)

A Differential Equation from the Theory of Neutron Thermalisation

The heavy gas model using a synthetic kernel leads to coupled equations for the determination of the neutron flux in a bare reactor. The very special problem of solving analytically the defining equation for the energy dependent neutron flux in a region for which there are no source terms is considered. (auth)
Date: February 1963
Creator: Wade, F J
System: The UNT Digital Library