The Battelle Research Reactor is a modified pool reactor located in a sparsely settled 500-acre tract owned by Battelle 13 miles west of Columbus, Ohio. The reactor has been operating since October 29, 1956, at power levels up to 1 megawatt. More than 300 megawattdays have been logged on the reactor with most of this operation at a power level of 1 megawatt. No serious incidents have occurred during the operation of the reactor. With only a few modifications the reactor will operate continuously at a power level of 2 megawatts. First, interlock will be added to the safety instrumentation to scram the reactor in the event of significant reduction in the flow rate of the primary coolant. Second, to provide additional margin of safety against the possibility of local boiling occurring in the core, the primary flow rate will be increased to greater than 1500 gpm. Third, a 700-gallon holdup tank will be added to the primary coolant system to allow for decay of the nitrogen16 formed in the coolant as it passes through the core. Holdup will reduce the dose rate at the surface of the pool to 4 mr per hr or less during routine 2-megawatt operation. …

A summary of the Cr data from the HRP in-pile corrosion program is examined in an effort to determine the Cr species present in such solutions under in-pile conddtions. Data from previous in-pile bomb and loop experiments pertinent to Cr behavior are tabulated, and correlations are offered to support a proposed model. It is pointed out that other interpretations of the same data are possible, and to obtain conclusive evidence as to the identity of Cr species in these solutions, especially designed experiments are necessary. (J.R.D.)

A description of hot laboratory metallography and techniques of operation are presented. These facilities and techniques provided a means of examining fuel elements that contain UO/sub 2/ after irradiation to high burnups. Some unusual irradiation characteristics of UO/sub 2/ were observed, and each effect is discussed. A complete explanation of the causes of such effects has not yet been obtained. (auth)

The advantages, disadvantages, and cost of constructing a auclear power reactor underground are outlinedData on underground construction of hydroelectric plants, other structures, and underground reactor projects in Norway and Sweden are reviewed. A hypothetical underground Experimental Boiling Water Reactor design and sketch are given with cost estimates(T.R.H.)

The techniques used in sampling, analyzing, and evaluating results for determining hazards from external radiation, airborne radioactive material, radioactive contaminants in mill effluents, and urinary uranium, as applied to the Monticello, Utah, uranium mill, are described. Corrective measures used by National Lead Company, Inc., at the Monticello Mill are described along with the results from later surveys which showed large reductions in the potential radiation hazards. Details are given of the methods used to determine personnel exposures to radioactive and silicosis-producing dusts, potential external radiation hazards and in assaying mill effluents for uranium and radium, assaying urine samples for uranium, as well as the standard operating procedures issued at Monticello to employees for preventing and/or controlling personnel exposures. (auth)

The energy and angular distributions of the gamma rays leaking from the BSF reactor were computed by (((((((((Abstract unscannable))))))))))

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This report details activities of the Fuels Development Operation for the months of July, August, and September 1958.

The study of the kinetics of layer growth in the aluminum -- nickel system and the effect thereon of applied pressure has been continued. Additional information has been obtained about the growth of the beta phase, and a method was developed whereby the kinetics of growth of the beta phase could be investigated. The implications of Vasileff's equations which provide the solution for interdiffusion in a three-phase two-component system have been examined semi-analytically, and quantitative insight has been gained into the kdnetics of interface movement. Finally, an investigation of the kinetics of interface movement and layer growth has been begun on systems which have less complicated phase equilibrium relationships than those existing in the aluminum -- nickel system. (auth)

The desigm and analysis of a mechanical transition joint between materials having different thermal coefficients of expansion are discussed. The analytical treatment is based primarily on the analysis of short cylinders. The specific desigm for the Zircaloy-2stainless steel core vessel joint in the HRT is discussed in detail. Brief summaries of preliminary designs and test results are included along with results obtained from the tests performed on the final design for the HRT. (auth)

The methods used to calculate the steady-state pressure and thermal stresses in the spherical portion or the HRT pressure vessel are presented, The stresses reported here were calculated using the methods considered most applicable st the present time. These methods yield stresses significantly greater than originally reported for the HRT because the calculated total heat generation rate in the vessel wall is greater, and its distribution is different. A comparison of tworegion (DP reflector) and single-region operation is made, showing very little difference between them insofar ss stresses are concerned. A limited amount of experimental heat balance data for the HRT vessel wall has been compared to the calculated values. Primarily on the bases of this comparison recommendations are made concerning further procurement of experimental data. (auth)

Maximum HRT dome wall temperatures for reactor powers up to 10 Mw were calculated for both an insulated amd uninsulated dome. Temperatures exceeding 315 deg C in the fuel solution flowing through the HRT dome section can cause phase separation which results in excessive corrosion rates. The results, based on very conservative assumptions, inticated wall temperatures exceeding 315 deg C could occur in the insulated dome when operating the reactor at 10 Mw. Using the same conservative assumptions, the analysis of the uninsulated dome indicated wall and bellows temperatures below 300 deg C. (auth)

The distribution of the heated effluents discharged by Hanford reactors to the Columbia River has been a matter of interest since the early design stage of the first reactors. The pattern of this distribution is a major factor in determining the extent to which a downstream reactor is affected by those upstream, as well as the localized effects on the ecology of the river. Pollutional characteristics of the effluents are three - heat load (or temperature increase), chemical contents and radioactivity. The latter has received the greatest attention in connection with potential personnel exposure and effects on river biota; it has been assumed however, and generally confirmed by sampling that the measure of distribution of any one of these characteristics in the saw an for the others. Observed distributions of radioactivity for various river and reactor flow rates are documented. Unfortunately, any extrapolation of those observed distributions to altered flow conditions of river regimes is of questionable validity. Mathematical models of the problem have been formulated but have been of little value due to the necessity of measuring certain parameters under the conditions for which a solution is desired. Even so, calculated distributions provide only general patterns and would not …

Stainless steel-base fuel components of thin plate-typs construction and containing a dispersion of enriched UO/sub 2/ have been successfully employed in powering the Army package Power Reactor. The stationary fuel compcnent proposed for operation in the second core loading of the reactor is discussed. The component is designed for radioactive service in pressurized water at 4504DEF and consists of eighteen composite fuel plates joined into an Integral unit or assembly by brazing. Design specifications covering the material and dimensional requirements as well as the operating conditions are discussed. Step-by-step procedures developed and utilized in manufacturing the component are presented in detail. (auth)

A basic study of the mechanism of deposition of small particles on cylindrical collectors in the presence of electrostatic forces has been made. Theoretical equations predicting the efficiency of collection have been derived and solved with a digital computer. The solution of these equations is shown. The deposition of liquid aerosol particles on cylindrical collectors was measured experimentally for a range of electrostatic conditions. The experimental results agree with the theory. An experimental study was made of the effect of electrical charges on aerosol particles on the filtration efficiency of glass fiber mats. Experiments were also made on the effect of placing a potential on a mat of fine wire and on filtration by a mat of a tangled wire dipole. (auth)

Prior to the installation of improved charging machines and charging techniques serious gouging of the soft aluminum fuel element jackets was not infrequent. A certain amount of mechanical abrasion also occurs as the element is pushed over the tube ribs in the course of the loading operation. To eliminate or at least minimize mechanical damage there has been some experimentation with hard anodic coatings applied to the aluminum fuel element jackets. This report is an evaluation of thinner anodic coatings which should develop lower mechanical stresses within the oxide and should be less subject to cracking.

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By means of 2-group, 3-region calculations the following features are investigated for a flux-trap reactor: finite fuel-layer thickness, moderation in the fuel layer, diffusion constant of the fuel layer, reflector thickness, and flux-trap radius. A 31-group calculation was used to study simultaneously finite fuel-layer thickness, moderation in the fuel layer, and epithermal absorptions as and fissions. The results obtained are very near those obtained for the idealized case in ORNL CF-58-1-4. (auth)

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The development of a matrix method of solving multigroup diffusion equations in nonmultiplying regions is described. The method is applied to a three-region shielding problem, and comparison is made with experimental results. Equations obtained by this technique can be solved with a desk calculator. (auth)

The objective of this program is to conduct a broad basic program of analytical and experimental research into the fundamental behavior of gas- lubricated bearings and to establish general design criteria for these bearings. The work to date has included both theoretical and experimental phases of hydrodynamic and hydrastatic lubrication phenomena, supplemented by a digital computer program. (W. L.H.)

This is the monthly report for the Hanford Laboratories Operation, March, 1958. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This is the monthly report for the Hanford Laboratories Operation, May 1958. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation area discussed.

This is the monthly report for the Hanford Laboratories Operation, June, 1958. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics, instrumentation research, employee relations, operations research, synthesis operation, programming, radiation protection, and laboratory auxiliaries operation are discussed.