None

At the present time, plants in the 100 to 500 Mw size range are more numerous and carry the greatest portion (over 50%) of the total steam-electric plant load in the US utillties industry. The contribution of plants of over 1,000-Mw capacity is increasing more rapidly than any other size classification and at present represents about 10% of the total capacity. By 1962 the TVA will have six plants with capacities of over 1,000-Mw. The largest steam-electric plant in the US is the TVA plant at Kingston, Tenn., with a nameplate capacity of 1,440Mw. Turbine-generator wits are also following a trend of ever-increasing size. In present construction, the 150 to 200 Mw size range for units ls the most common and represents the greatest contribution to capacity. Two units of 500-Mw nameplate rating each, the largest in the US, are on order by the TVA, and an 80 Mw unit is contemplated. (auth)

Volatility Pilot Plant Mark III Fluorinator is a doublechamber type vessel, each chamber 2 1/2 ft by 16 in. outside diameter separated by a 5-in. pipe 15 in. long. ASME flanged and dished heads are used for the chamber tops and conical sections with a 60 deg apex angle for the chamber bottoms. A new furnace designed to maintain the complete lower chamber (molten salt+ freeboard) above melt temperature is to eliminate past experiences of salt solidification on the wall, heads, and in or on the internal process lines. External pipe runs are autoresistance heated to allow melting and drain back of salt plugs. The upper chamber serves as a gas de-entrainment and solids precipitation device to retain most of the entrained salt and condensable fluorides in the 100 to 400 deg C range. (auth)

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 …

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 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)

Results are presented of an evaluation of nuclear safety and raaiation control related to the shipment, mechanical processing, and storage of SRE-1 fuel elements. (auth)

An automatic device for tracing the waveform of a repetitive oscilloscope pattern has been developed. The waveform is accurately reproduced and magnified by a conventional X-Y recorder. Because optical and pulse techniques are used the system is capable of reproducing signals displayed on even the fastest available oscilloscopes. When useil with a high-frequency traveling-wave oscilloscope, the method is applicable to phenomena in the millimicrosecond region and is capable of utilizing time resolution down to 0.1 m ic sec. Deflections as small as one micron niay be detected. In addition to making oscilloscope measurements faster and more convenient, many of the sources of distortion normally encountered in oscilloscopes are eliminated. (auth)

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)

This report addresses the AEC symposium on particle-fluid mechanics

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)

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 …

The thickness of an oxide film on phosphor bronze helices was determined by first establishing the oxygen content of the helix "as received" and after cleansing with nitric acid. Based on the assumption that the difference between the two values was the oxygen in the film, and that the film consisted entirely of cupric oxide, the thickness of the film was calculated from the density of cupric oxide, weight of film, and surface area of film. A value of 1080 A was calculated as the thickness by this method. (auth)

After two batches ( approximately 340 kg) of fluoride salt from the ARE were reprocessed, a pilot plant operations were terminated because of a leak through which an estimated 780 g of uranium (as UF/sub 6/ escaped. Of the 21 kg of highly enriched uranium in the feed, 93.12% was collected as UF/sub 6/ product, 0.13% represented measured losses, and 3.72% was unaccounted for (leak). An additional 3.03% was reclaimed from NaF beds and equipment washes. The produce met both chemical purity and activity specifications for product level UF/ sub 6/. Decontamination from fission products was essentially complete. A gross gamma decontamination factor was apparently limited by the low activity of the feed salt. (auth)

The basic theory of operation of the triggered spark gap is established, and qualitative and quantitative engineering design data are given. From the basic twoelectrode gap, a three-electrode or triggered gap model is established with its static and dynamic triggering characteristics shown. Several geometry conditions such as gap spacings trigger electrode hole sizes and insulator effects are discussed, showing their influence upon the triggering mechanism. A suggested trigger mechanism is given based on that proposed by Sletten and Lewis for the trigatron and modified to fit the present analysis. (auth)

A simple model of time-independent neutron transport on a line as a stochastic process, using the method of invariant imbedding, is considered. Non- linear equations for the expected values (flux) are also obtained and solved, the results are compared with the ordinary linear theory, and possible advantages of the new formulation are cited. Generalizations to a large class of transport problems are discussed. The nonlinear timedependent operator for transport in one dimension is considered in detail. It has a pure point spectrum, and expansion theorems can be proved. These results contrast with those for isotropic one-velocity neutron transport in the infinite slab. Here there are only a finite number of points in the point spectrum, with a halfplane in the continuous spectrum. Approximations to the eigenvalues and eigenfunctions for the slab case, as well as extensions to the multivelocity problem, are mentioned. There is a brief discussion of recent spectral and expansion theorems for very general geometries. (auth)

Changes in mean expansion coefficients upon annealing uranium sheet that had been rolled to 80% reduction in thickness at room temperature indicated that three different preferred oriontations could be developed upon recrystallization. One preferred orientation, which is essentially the same as that of the as-rolled material, resulted from annealing for long times at 360 deg C or at a lower tempcrature; a second type was created by annealing for moderate times between 400 and 600 deg C; and the third accompanied grain coarsening at 650 deg C. The microstructures of the as-rolled and annealed specimens were extremely heterogeneous because of the large grain size present prior to final fabrication at room temperature. The as-rolled structures consisted of heavily deformed areas and smaller quantities of lightly deformed material. The annealing of the former was characterized by initial creation of very fine recrystallized grains which were absorbed later by discontinuous growth of larger grains. Lightiy deformed areas, upon annealing, first exhibited recovery by polygonization and then underwent normal recrystallization. (auth)

The burns to the skin of anesthetized rats were determined for the thermal radiation pulses of a carbon arc on a hot-wet uniform when spaced 5 mm from the skin. The radiant exposures to cause burns resulting in eschar were tion pulses corresponding to 250, 1000, 2900, and 10,000 kiloton detonations, respectively. The threshold lesions were caused by volatile products not associated with ignition. The associated temperatures were recorded. (auth)

The Army Gas Cooled Reactor System Program includes water moderated heterogeneous reactor (Gas Cooled Reactor Experiment I), a graphite moderated homogeneous reactor (Gas Cooled Reactor Experiment II), a mobile gas cooled reactor (ML-1), and the co ordination of thc Gas Turbine Test Facility. The progress of each project, the associated tests and data evaluation, the applicabie design criteria, and the fabrication of reactor components are briefly summarized. (For preceding period see IDO-28538.) (W.D.M.)

Production of Pu from separations plants was only 58% of April commitment because of Purex difficulties. UO{sub 3} production, shipments met schedules. Pu shape production and shipments exceeded forecast by 14%. Purex HS column, repaired Oct 1958, developed another leak and was bypassed April 18, resulting in Pu and U that required reprocessing. A Palm recovery run at Purex with all- reducing flowsheet, resulted in 87% recovery and excellent decontamination of product. The prototype dual-pass silver reactor in Purex C-cell plugged with offgases. Processing of unclarified feed through Purex solvent extraction continued. Redox dissolver batch sizes for E-metal processing were increased from 1.75 to 2.0 tons. Testing of first extraction cycle acidic flowsheet at Redox continued, with Np losses to HAW being below detection limit. Ru in 1AFS stream increased 10-fold F.P. activity but was removed in acid deficient U cycles. A sulfamic acid process is being explored for dissolving Pu metal. Scope design of Redox dissolver and RMA line replacement at Z plant was completed. Shielding effectiveness of medium and high density x-ray lead glass was compared.

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

Chemical control of the SM-2 was evaluated both as a partial substitute for burnable poison in the fuel element meat and as a means of improving plant performance. Based on a review of existing information, boric acid was chosen as the reference soluble poison. It was shown that 60% of the burnable B/sup 10/ in the fuel element matrix could be replaced by soluble B/sup 10/ in the coolant without impairing plant stability during load transients. The feasibility of improving power distribution and reducing the number of control rods by supplementing the burnable poison with chemical control was also demonstrated. A preliminary design of an injection and removal system was prepared for the SM-2. (auth)

This document details activities of the Fuels Preparation Department during the month of April 1959. (FI)