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Neutron Diffraction Study of High Temperature Annealed Beryllium Oxide

Description: 1. X-ray and neutron diffraction studies were caried out on the crystal lattice of beryllium oxide annealed at 2000 degrees. 2. It was determined that neutron diffraction data confirms X-ray conclusions of the positions of beryllium atom positions in the crystal lattice of beryllium oxide. 3. From neutron diffraction data the values of the temperature fact B + 0.92 and the Debye characteristic temperature theta = 602 +- 13 degrees K were found.
Date: 1962
Creator: Kuleshov, E. M. (Evgeniĭ Mitrofanovich); Saduhov, G. G.; Sokotova, Z. A. & Hogg, S.
Item Type: Refine your search to only Report
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An Apparatus for Dissolving Irradiated Fuel Specimens and Accurately Sampling the Solution

Description: 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.)
Item Type: Refine your search to only Report
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An Analysis of Instrumental Errors Affecting the Performance of a Schultz-Type Texture Goniometer

Description: 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.
Item Type: Refine your search to only Report
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Determination of Beryllium, Thorium, and Uranium in Sulphuric - Phosphoric Acid Mixtures

Description: 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 ac… more
Date: September 1962
Creator: Florence, T. M. & Shirvington, P. J.
Item Type: Refine your search to only Report
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Use of a Radioisotope Method to Measure Flow in the HIFAR Light Water Cooling Circuit

Description: A radioisotope method has been used to measure the flow in the light water circuit of HIFAR. A mean value of 756 pounds/sec was obtained which is in fair agreement with conventional Dall tube method. Attempts to measure the flow through individual cooling towers were not entirely successful, but some useful information was obtained.
Date: February 1962
Creator: Ellis, W. R. & Beswich, C. K.
Item Type: Refine your search to only Report
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An Apparatus for Differential Thermal Analysis and its Use in the Investigation of Some Beryllium Compounds

Description: 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.
Item Type: Refine your search to only Report
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Measurement of the Prompt Neutron Lifetime in HIFAR

Description: The reactor transfer function of HIFAR has been measured at low power and compared with the calculated response determine the prompt neutron lifetime. Lifetime values in the range 600 to 800 microseconds, depending on the position of absorbers withing the core and reflector , were obtained with an estimated error of less than 100 microseconds.
Date: February 1962
Creator: Parry, J. K.
Item Type: Refine your search to only Report
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The Reprocessing of Beryllium-Base Reactor Fuels : a Chemical Feasibility Study of a Modified Thorex Process for the Recovery of the Uranium and Thorium

Description: Stable solutions of basic beryllium nitrate can be formed with beryllium concentrations up to 9M, and an NO3/Be mole ratio as low as 1:1. The efficiency of basic beryllium nitrate as an agent for salting out uranium into a tributylphosphate/kerosene solvent has been compared with that of other salts. It appears possible to separate uranium and thorium from beryllium and fission products using a modified Thorex process in which beryllium nitrate replaces aluminum nitrate.
Date: August 1962
Creator: Farrell, M. S.; Orrock. B. J. & Temple, R. B.
Item Type: Refine your search to only Report
open access

Irradiation Damage Aspects of Dispersion Fuel Elements for the H.T.G.C. Reactor

Description: The concept of a dispersion fuel element is discussed with particular reference to irradiation damage. The application of this concept to the A.A.E.C. H.T.G.C. reactor system is outlined and the limitations imposed by irradiation damage considerations are discussed. The maximum desirable heavy metal - beryllium ratio (i.e. U+Th:Be) for the various systems under consideration should be about 1:55 for the system (U,Th)Be13 in Be, 1:13 for the system (U,Th)O2 in Be, and 1:8 for the system (U,Th)O2… more
Date: June 1962
Creator: Hickman, B. S. (Brian Stuart)
Item Type: Refine your search to only Report
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Cost Estimation for Nuclear Reprocessing Plants : a Comparison of Methods

Description: 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… more
Date: March 1962
Creator: Alfredson, Peter George & Cairns, R. C.
Item Type: Refine your search to only Report
open access

Preliminary Experiments on the Dissolution of Beryllium Based Fuels in Ammonium Fluoride Solutions

Description: Some preliminary measurements have been made of the rate of dissolution of beryllium when refluxed with ammonium fluoride solution. The rate of dissolution exhibits pseudo first order dependence on the "free" fluoride concentration defined as the concentration of total fluoride less that assumed to be present as BeF4. The solubility of uranium metal in ammonium fluoride - beryllium fluoride solutions increases with free fluoride concentration, where the uranium is present in solutions as U(1V).… more
Date: May 1962
Creator: Whitfield, H. J.
Item Type: Refine your search to only Report
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Elastic Thermal Stress in Reactor Fuel Elements -- a Comparative Study of Various Shapes

Description: A method for comparison and evaluation of thermoelastic stresses is given for a range of fuel element shapes based on parameters available from the initial study of a reactor system. The shapes studied, in descending order of stress level are circular rods, concentric tubes, flat plates, and a matrix of circular holes.
Date: August 1962
Creator: Binns, Ian M.
Item Type: Refine your search to only Report
open access

Dissolution of High Density Beryllia Compacts

Description: The dissolution of dense beryllia was studied in a variety of reagents. The dissolution rates were too slow to be of practical importance except those for hydrofluoric acid, sulfuric acid, and mixtures of sulfuric and phosphoric acids. The reaction with hydrofluoric acid was studied in more detail in an attempt to throw some light on the dissolution process. The initial dissolution rate appeared to be proportional to the square of the acid concentration between 0 and 20M. An apparent activation… more
Date: September 1962
Creator: Ekstrom, A.; Farrell, M. S. (Michael S.) & Temple, R. B.
Item Type: Refine your search to only Report
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The Effect of Departure from the Optimum Operating Conditions on the Production Cost of Electricity from Gas-Cooled Nuclear Power Plants

Description: The second partial differentials of the production cost equation are derived in a generalized and non-dimensional form in order to determine the effect on production cost of electricity from a gas-cooled nuclear power plant of departure from optimum operating conditions. Fuel element surface temperatures up to 650 degrees C, production costs up to 1d. (A)/kwh and reactor coolant temperature rises up to half the maximum surface temperature are included. The most significant parameter is the rati… more
Date: 1962
Creator: Binns, Ian M. & Pulley, O. O.
Item Type: Refine your search to only Report
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A Monitor for the Continuous Determination of Deuterium

Description: Details are given of a monitor for the continuous determination of deuterium in helium. Excess oxygen is added to the gas stream and the oxygen concentration determined before and after passage of the gas through a deuterium-oxygen recombination unit. Oxygen concentrations are measured with galvanic cells. The accuracy is better and +- 10 percent in the range 200 - 5000 v.p.m. deuterium. operating instructions for the Lucas Heights equipment are given.
Date: December 1962
Creator: Morgan, R. R. T.
Item Type: Refine your search to only Report
open access

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

Description: 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.
Item Type: Refine your search to only Report
open access

The Microbiology of Heavy Water in the HIFAR Reactor

Description: The high flux research reactor HIFAR contains ten tons of heavy water which acts as moderator and primary coolant. Over an eighteen months period regular microbiological examinations have been carried out on samples of heavy water taken from various parts of the circuit. The heavy water circuit provides an interesting opportunity for the study of microorganisms because of the high isotopic purity (greater than 99.6 per cent.), and the high chemical purity of the heavy water in the reactor. Furt… more
Date: June 1962
Creator: Davis, P. S. & McPherson, G. G.
Item Type: Refine your search to only Report
open access

Automatic Solution of Optimum Design Problems on a Digital Computer

Description: 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.
Item Type: Refine your search to only Report
open access

Reactions of Preoxidized Beryllium Powder in Moist Carbon Dioxide

Description: Breakaway corrosion of Be in moist CO2 can be avoided if the Be is fabricated using preoxidized powder. The powder is preoxidized by heating in dry O/sub 2/. Preoxidation of Be powder was measured as a function of temperature and time of heating in O/sub 2/. The subsequent reactions of the preoxidized powder in moist CO/sub 2/ at 700 deg C were studied and the effect of increasing amounts of added oxide was measured. A model is proposed to explain the inhibition of corrosion by added oxide. (au… more
Date: June 1962
Creator: Adams, R. B.; Price, G. H. & Stuart, W. I.
Item Type: Refine your search to only Report
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