From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."

Report discussing the coarsely crystalline autunite in granitic rock near Mt. Spokane, Washington. "This report is an abstract of a paper with the same title that is planned for publication in the American Mineralogist."

The presentation includes a very general outline of the program, a semi- detailed flow diagram which emphasizes the physics and control aspects of the calculation, and then a detailed flow diagram and listing of the program (which is written in Fortran). Explanatory notes accompany thc diagrams. Following the notes on the program, master lists detailing thc roles of the sense switches, sense lights, pauses, and stops are presented. The operating instructions are then given, followed by a sample problem, including detailed information on input data. The theoretical discussion has been kept primarily in the appendices, and is generally in outline form with references, rather than in full exposition. (auth)

''Blackaess theory'' is described as a class of procedures for matching a high order transport approximation in one region to a low order approximation in a second region. The matching conditions are presented as a generalization of the Marshak boundary conditions. The blackness coefficients necessary in setting up the conditions are defined and tables are given for slab geomrtry. A method which allows all regions to be treated by means of the blackness coefficients is developed and applied to two region cells. Numerical results are compared with other approximations in situations typical of those encountered in resonance capture and thermal utilization calculations. (auth)

This code finds inelastic cross-section matrix elements (transfer matrix) for hot monatomic moderator for multigroup calculations by numeric- analytic double integration of Cohen's formula. Several approximations to the actual neutron density ean be used as weight functions over the velocities of the initial groups. Modified and supplemented results are presented on binary cards and/or tape for direct input into the Argonne Transport Theory Codes or the SNG Code, or for offline output. (auth)

This report addresses the chemical technology divisions' monthly report for chemical development.

please delete the no. 17076<><DSN>13:017077<ABS>The P/sub 1/ multigroup code was written for the IBM-704 in order to determine the accuracy of the few- group diffusion scheme with various imposed conditions and also to provide an alternate computational method when this scheme fails to be sufficiently accurate. The code solves for the spatially dependent multigroup flux, taking into account such nuclear phenomena is slowing down of neutrons resulting from elastic and inelastic scattering, the removal of neutrons resulting from epithermal capture and fission resonances, and the regeneration of fist neutrons resulting from fissioning which may occur in any of as many as 80 fast multigroups or in the one thermal group. The code will accept as input a physical description of the reactor (that is: slab, cylindrical, or spherical geometry, number of points and regions, composition description group dependent boundary condition, transverse buckling, and mesh sizes) and a prepared library of nuclear properties of all the isotopes in each composition. The code will produce as output multigroup fluxes, currents, and isotopic slowing-down densities, in addition to pointwise and regionwise few-group macroscopic cross sections. (auth)

Submitted to Rensselaer Polytechnic Inst. The computation of reactor characteristics over a fuel cycle in a way suitable to the investigation of the control aspects of the reactor problem is considered. The dynamic problem including as independent variables the neutron energy, the spaces and time was studied. An additional condttion of versatility in the method used to obtain the solutions is necessary to explore the control aspects of the problem. The normal possibilities of the analog computers were surveyed, and a method was found to solve the reactor dynamic problem. The classical approach of considering the neutron energy dependency in groups and the spatial dependency in reactor regions is used. Only cases of regular symmetry are considered, so that the reactor three dimensional configuration is reduced by analytical methods to the study involving one space coordinate. Time is considered as a continuous variable. The Mighty Mouse Deactor is simulated, and the analog results are compared against published data. With the spatial dependency represented by three core and three reflector regions, the fast and slow flux distributions are within 5% of the digital computer solution of the same problem. At the end of the fuel cycles the flux distribution is essentially …

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

In this brief bibliography the emphasis is on new cushioning materials for packaging and on environmental testing and performance of these materials. The survey is not intended to be exhaustive. The following sources were consulted: Technical Abstract Bulletin of the Armed Services Technical Information Agency, Sandia Unclassified Documents Catalog, U. S. Government Research Reports, Technical Information Pilot of the Library of Congress, and Engineering Index. (auth)

Measurements were made of the product of surface tension (ϒ) and the contact angle (θ) of liquid plutonium vs solid tantalum and of the density of liquid plutonium (p) as functions of temperature between 655 and 960°C. The following values were obtained: ϒ cos θ = 1030 - (0.967)T d/cm and p = [17.56$sub 7$ - (1.45$sub 1$ x 10$sup -3$)T] ± 0.021 g/cm$sup 3$. A single determination was also made of the liquid density of a plutonium-7.93 atomic percent iron alloy and he following value obtained: p = [16.88 - (1.36$sub 9$)T] ± 0.012 g/cm$sup 3$.

None

Eight boiling reactors, BORAX I, II, III, IV, EBWR, LITR, VBWR, and SPERT I,have been operated to date, and a considerable amount of information exists in regard to their tendencies toward self-induced power oscillations. Data are presented on the following characteristics of the oscillations: power, pressure, temperature, reactivity amplitudes, and their rate of change: thresholds, and harmonic content. Results from three techniques of measuring the reactor transfer function are presented: the rod oscillation, the reactivity step, and the autocorrelation methods. Quantitative definitions of instability are introduced. Theoretical annlysis of these reactors' kinetic behavior, based on a simple model where steam void feedbacks dominate, shows an adequate understanding of many of the phenomena, some even quantitntively. It is concluded that it is possible within the framework of existing experimental and theoretical boiling reactor dynamic technology, to design these reactors with reduced instability limitations on the power, and obtain power densities in excess of the current 50 kilowatts/liter of core. (auth)

The characteristic square output currert pulse from a discharging coaxial cable has been utilized to explode wires of 1-mil diameter. The primary pulse duration was 3 mu sec and was variable in amplitude to a maximunn of 600 amperes. Voltage and current waveforms were recorded on a high-speed oscilloscope. Resolution of the system is better than 10/sup -8/ sec, thus enabling accurate determination of the resistance history of the malerial being studied. A survey of the behavior of various metals is presented, and the results of certain parameter studies, such as, geometry, external environment, and current density, are discussed. It is shown that end effects contribute to the measured length of the sample, and that the energy to burst is dependent on current density. A new experimental system capable of producing square current pulses with an amplitude of 2000 amperes is described. (auth)

To better understand the solvent extraction process much effort has been and is being expended at ORNL and elsewhere to measure reaction kinetics of the extraction reactions. To date these efforts have been largely unsuccessful, due to the attempt to apply homogeneous reaction kinetics to two-phase systems. An optical method has been devised for analyzing the concentration profile in the vicinity of a quiescent interface during steady-state diffusion at rather large molecular fluxes. The system under study is the extraction of uranyl ion from water by a TBP solution. Considerable effort has been directed to eliminating leaks in the diffusion cell and testing the optical system/

A study of the equiibrium sorption isotherms and rates of U sorption on Dowex 21K is in progress. Data which show the effects of uranium concentration in solution on resin loading are presented Fuel reprocessing experiments are reported in which efforts were made to reduce Cl- in Darex dissolver solution to < 350 ppm for the extraction phase. The best method of Cl/sup -/ reduction appears to be operation with a down draft condenser and an air sparge. A check- out dissolution min in the 6 in. glass dissolver with a prototype APPR fuel element is reported, and data on dissolution time and composition of reacted products are given. Data on filtration rates for Darex solutions expected in large-scale operations are tabulated, and graphs illustrating the effects of pressure drop and filter aids on filtering rates are presented. Tests on washing U from filter cakes indicate that U can be removed to any desired level. Viscosity, density. and boiling points as a function of temperature or pressure were determined for two Darex solvent extraction feed solutions; data are presented grahically, and results of chemical analyses are tabuated. Demonstation runs for Sulfex and Zirflex dejacketing flowsheets were made. Results indicate that …

The extraction reaction kinetics and the liquid diffusivities are being studied by measuring the concentration profile in a column of liquid containing an interface. The determination of the equilibrium sorption isotherms and rates of sorption of U on Dowex 21K is reported. Flowsheet development and modification are reported for the Darex process. U was shown that the hydrochlorination of Zr-U alloy fuels with HCl gas contain- ing CO/sub 2/, H/sub 2/O/, and O/sub 2/ impurities increases the quantity of HNO/sub3/ insoluble U losses in the uranium chloride product. During the dissolution of spent enriched oxide fuel cores in a dissolver geometricslly safe only in the bottom dissolution area the dissolution off-gas may entrain critical amounts of fine undissolved fuel particles to the enlarged non-critically safe upper portion of the dissolver. Preliminary tests were made to determine the likelihood of fuel fines being entrained in this manner during the dissolution. Solvent extraction studies are being made to assist the Hanford Atomic Products Operation to adapt the Redox process for the recovery ot U from spant stainless steel-type power reactor fuels. Preliminary hot cell tests of the Zirflex and Sulfex flowsheets -Here completed. Batch dejacketing and core dissolution of each of sixteen …

In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.

An effort is being made to determine the equilibrium sorption isotherms and rates of sorption of U on the anion exchange resin Dowex 21K. In the Darex process investigations included: batchwise Cl/sup -/ removal and feed adjustment, continuous dissolution, feed clarification, filtration rates for solutions, effect of pressure drop and fllter aid on flltration rate, cake washing and removal, properties of solutions, and properties of sands and filter aids. Batch dissolutions of irradiated' Consolidated Edison Fuel and PWR blanket pins were made to demonstrate the Sulfex and Zirflex dejacketing flowsheets, respectively. Dissolution studies to obtain rate and penetration data for UO/sub 2/ in HNO/sub 3/ solutions were begun. Preliminary shearing studies with the 120 ton hydraulic Manco shear with a prototype fuel bundle showed that a line contact shear closes the fuel bearing tubes to an extent detrimental to good leaching. A series or experiments was performed to determine the amount of fission products evolved when different types of wastes were dried and calcined. (W.L.H.)

In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.

The status of the Eurochemic Plant, Mol, Belgium, is summarized, and the Eurochemic organization is given. The anticipated United States assistance through June 1959 is listed. (auth)

Presented at Inst. of Environmental Engineers STAMeeting!, Chicago, April 1959. A brief discussion is presented of the progress over the last seven years of the environmental laboratory at Sandia Corporation. (W.L.H.)

Abstract: "An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fallout. Pocket ionization chambers were used for measurement of the radiation-field strength. Fallout was simulated with distributed and point-source configurations of Co-60 and Ir-192 sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation."

An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fall-out. Pocket ionization chambers were used for measurement of the radiation-field strength. Fall-out was simulated with distributed and point-source configurations of Co/sup 60/ and Ir/sup 192/ sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation. (auth)