Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

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A generalized correlation for the liquid fraction in twophase flow is presented which is proposed for use with all iluids, including liquid metals. The correlation is based on isothermal, two-phase, two-component liquid fraction data for liquid Hg--N/sub 2/ and water-air. Liquid fraction is shown to be a function of the Martinelli flow modulus and liquid/gas density and viscosity ratios. Good correspondence is indicated between the liquid fraction predicted by this correlation and the Martinelli-Nelson correlation for steam, experimental data for steam, and experimental data for Santowax R. Prediction of liquid fraction by this method is shown for Na, K, Rb, and Hg. Application of the method to boiling Hg, for a range of temperatures and exit qualities, is demonstrated for SNAP systems. (auth)

Pressure drop and vibration characteristics were determined for an 8-rod fuel element model of the design intended for use with uranium carbide (UC) in the Hallam Nuclear Power Facility (HNPF). Measurements with water as the test fluid were converted to equivalent values for sodium, the HNPF coolant, using the principles of dimensional similitude. Initially UC elements will be concluded in an HNPF core loading comprised primarily of 19-rod U-Mo fuel elements. In this core loading, the UC fuel element requires 17.5 lb/sec of sodium coolant at a core pressure drop of 11 psi. The measured fuel element pressure drop ranged from 0.27 to 5.8 psi over the sodium flow range from 3.5 to 17.4 lb/sec. The existing HNPF variable orifice can adjust flow for this fuel element over the range from 5.7 to 21 lb/sec at a core pressure drop of 11 psi. No significant vibration of the fuel rods was induced by the flow of water. (auth)

The conversion of strontium-90 to strontium titanate heat source pellets is described. Encapsulation of the fuel in Hastelloy C containers and necessary leak testing, decontamination and calorimetry procedures are covered. Loading of the SNAP 7B thermoelectric generator was accomplished. (auth)

Current-voltage characteristics of a cesium-on-tantalum thermionic converter with a collector temperature comparable to that of the emitter were obtained for a variety of electrode temperatures and cesium vapor pressures. The results show that for emitter temperatures in excess of 2000 deg K, power outputs of a few watts per square centimeter can be obtained when the ratio of collector temperature to emitter temperature is as high as 0.75 to 0.80, which is the required range for best performance of a radiation-cooled Carnot engine, and that at temperature ratios above 0.80 the power output is insensitive to changes in electrode spacing for ratios of spacing to electron mean free path greater than 100 at a cesium vapor pressure of 5 torr. (auth)

A review is presented of various types of solutions of metals in molten salts, especially in their own molten halides. With relatively little reference to the older literature, the progress made in the last 20 years is discussed. Roughly, the solutions are classified into two groups: The metal may retain, to some degree, its metallic properties in the solution, or it may lose them through strong interaction with the salt solvent. The alkali-metal systems are typical examples of the former type, while solutions of cadmium or bismuth represent the second. Equilibrium phase diagram data are presented in detail for many metal- salt systems. These include critical solution temperatures, that is, temperatures above which metal and salt are miscible in all proportions. Electrical conductivity is singled out as a most significant physical property from which conclusions on the state of the electron in the solution may be drawn. In the electronically conducting solutions, notably of the alkali metals, the electrons may be thought to resemble F centers in color-center colored crystals. In solutions where electronic conductance is absent, monomeric, dimeric, and even more highly poly, merized species of the solute metal in a low valence state must be assumed to occur. …

Information required to obtain authorization to receive and use a fast critical assembly for operation with the General Atomic linear accelerator is documented. The analysis offers evidence showing that operation of the assembly will create no undue risk to the health and safety of the public or the personnel of the Laboratory. Experiments with the accelerator pulsed fast assembly will consist primarily of measurements of neutron yield and pulse shape produced by the electron pulses from the Linac impinging on the spherical metal reactor. (N.W.R.)

Explosion containment vessels for containing from 2,000 to 3,000 five ton nuclear explosions are considered. Analysis methods appear adequate and lowest weights using the most advanced materials available in the next five years are projected.None of these materials can be fabricated today and all require extensive development. Present material technology limits the choice of materials and defines the weight. The addition of safety factors and fixtures (nozzles, etc.) will add to this weight considerably, and may well radically alter the vessel response. Improvements in the strength weight ratios of metals and glasses over those considered in this report do not appear reasonable at this time. Winding schemes to utilize the high strength of steel wires and somehow maintain a reasonable thickness appear to offer the most promise. A `ductile` beryllium would of course offer vast improvement, but no indications that this is being developed have appeared and all presently known beryllium is much too brittle.

An information storage and retrieval system (PIC) was developed, utilizing the IBM 7090 computer, for handling data pertaining to the effects of neutron irradiation on metals. The input includes a reference identification, an appropriate abstract or extract summarizing the article, code identification parameters analogous to those used by the ASM-SLA Literature Classification System, and special codes identifying relevant irradiation and testing parameters. The output contains the same data plus printing out the meaning of all special codes. Presently, the information storage consists of more than two hundred references representing several thousand lines of information. The system is both general and definitive, permitting the selection of a single piece of information or of many references dealing with a general field. It is possible to select material on the basis of one or more of the following factors: material, general or specific; type of literature; general or specific property such as mechanical tests or tensile tests; conditions of irradiation including type and level of flux, integrated flux, irradiation temperature, and reactor environment; test conditions such as temperature and environment; and general variables that might be controlling such as strain rate, specimen geometry, grain size, and fabrication history. It is felt that this …

The theoretical development, statistical treatment, and application of hot channel factors in compact SNAP reactors as represented by the SNAP 8 experimental core loading are presented. The channel and rod power effects of variation in the concentrations of uranium, hydrogen, and poison in the fuel rods are given. The statistical distributions of all variables are examined. A random selection of rods and channels is compared to the actual SNAP 8 configuration, with no difference noted. Confidence limits are set on hot rod and hot channel factors. Various other factors and aspects of the problem are discussed. The results of the study showed that the hot channel factors may be reduced to less than +2% over the nominal power, as opposed to a hot channel factor of about +10% as previously determined by empirical methods. (auth)

= 9 6 < ? < 0 t and fabrication method on irradiation stability, thermal conductivity, and hot hardness of uranium carbide were determined. Hypostoichiometric and stoichiometric uranium carbides prepared by both powder metallurgy and skull casting and hyperstoichiometric cast carbide were tested. The preparation of 12% enriched uranium carbide specimens for irradiation testing was completed. Sintered specimens were 98% of theoretical density for hypostoichiometric uranium carbide and 92 to 93% of theoretical for stoichiometric uranium carbide. All cast specimens were above 98.7% of theoretical density. Five different specimens, 4.4 and 4.8 450 deg C in a 0.1 wt% carbon, cast material and sintered material, and 5.2 450 deg C in a 0.1 wt% carbon, cast uranium carbide, were canned separately in niobium-1 wt% Zr and inserted into each of three capsules. The fuel specimens in capsule UNC-1-2 were contained in a sodium bond. This capsule was removed after 15,000 MW-d/ton U burnup in the MTR. The specimens in capsule UNC-1-3 were canned using an interference fit between cladding and fuel. This capsule was removed from the MTR after 14,440 MW-d/ton U burnup. Fuel surface temperatures ran in the range of 650 to 870 un. Concent 85% C and center-line …

The salt velocity technique for measuring coolant flow through a SNAP 8 tri-cusp channel was studied and developed. The parameters important in obtaining reproducible data were investigated and a test procedure, which yields dath of good precision, was developed. Dath were taken on a tri-cusp channel with flush circular electrodes (0.125 inch O.D.) as well as on a tri-cusp channel with parallel plate electrodes (0.006 inches thick, 0.250 inches long), which were situated 0.050 inches apart and protruded 0.040 inches into the stream. The data are presented as the ratio of U/sub exp//U/sub avg/ where U/sub avg/ is calculated by means of a flowrator and channel geometry. It was found that in the tri-cusp channel for a range of Reynolds Numbers of 11,000 to 25,000, a radial velocity profile could not be sensed. The peripheral velocity profile over the central baif of the cbannel appeared to be flat and relatively.independent of the Reynolds Number. The data were compared with similar work of Palmer and Swanson in a qualitative and quantitative manner. Reasons are given for using a single calibration factor in the hydraulic model testing of S8DS core. While some slight modifications should be made to further improve the accuracy …

This document has been prepared for internal use by the General Electric Company to serve as a program for evaluating reactor instrumentation and safety circuit equipment needs. It is intended that this document be used as a guide for defining, planning and scheduling engineering effort; budgeting of capital money; and project planning for new instrumentation systems. Effort will be made to periodically evaluate the status of the programs presented and provide updating information accordingly.After a plant has been built and operated for a number of years, it becomes apparent to operating and engineering personnel that certain modifications in controls and monitoring systems would provide both tangible and intangible benefits. Systems which were once thought to be the primary points of control shift in importance as others become recognized. As time passes this shifting spreads the main control focus from the central control desk to various other areas in the control room. Production rate increases cause instrument ranges and scales to be changed so that information on the process can still be obtained from existing equipment. Response times, sensitivity, limits, and time constants which were figured for one level must be used or revised for new levels. Further, it is discovered …

A set of 23-group neutron cross sections for use in the calculation of neutron thermalization and thermal neutron spectral effects in SNAP reactors is compiled. The sources and methods used to obtain the cross sections are described. (auth)

An engineering study was recently performed by Separations Process Design Engineering to determine the feasibility of processing the total Chemical Processing Department production load in the Purex Plant. This document summarizes the results of the study and the basis for the scope design or the multipurpose dissolvers for the Purex Plant.

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In studies of the effect of alloying elements on the rate of dissolution of Al in mercury-catalyzed nitric acid, it was observed that Co, Ni, and Si present at concentrations of 1 to 2% have significant passivating effects. Fe was slightly catalytic. Passivation due to Si was partly overcome by contacting the passive alloy with active, high-purity Al. Increased catalyst concentration improved the rates when Ni and Si were present. Neither approach was effective when Cu was the passivating element. For application to nuclear fuel reprocessing, it is suggested that for minimum reprocessing costs the potentially passive Al alloys not be used in fuel elements or that, failing this, electrochemical activation techniques be applied at the processing plant. (auth)

The operations in a process proposed for recovering uranium from spent uranium-- zirconium alloy fuels, including collecting the volatilized chlorination products (mainiy zirconium tetrachioride and uranium pentachloride) in boiling water, concentrating the resulting solution, lowering the freezing point by removing chloride with hydrogen peroxide, and recovering uranium from the 5 M Zr product solution by solvent extraction with tributyl phosphate in Amsco diluent, were investigated in the laboratory and appeared to be reducible to large-scale practice. The high temperature chlorination equipment would also be adaptable for burning graphite matrix fuels and when combined with Darex equipment for processing fuels containing stainless steel, molybdenum, or aluminum may provide the basis for a feasible universal fuel processing system. (auth)

A general description is given of the Pre-Buggy chemical explosive experiments. These experiments consisted of a series of single- and multiple- charge detonations designed to refine our knowledge of channel size as a function of charge spacing, and to obtain data on venting of explosion products from a row of spherical charges detonated in alluvium. A basic series of six single-charge detonations and four multiple-charge detonations of five charges in a row was executed in Area 5 of the Nevada Test Site from November 1982 through February 1983. Each charge contained 1,000 pounds of nitromethane with a La/sup 140/ tracer. Preliminary examination of the results indicates that: (1) When charges were spaced at 1.0 single-charge crater radius, the channel depth and width were larger than the diameter and depth of a single-charge crater. (2) Small increases in spacing resulted in considerable reduction of channel depth and a smaller reduction in width. (3) The channel shape at spacings of 1.5 single- charge crater radii was very uneven. (4) When the ratio of the depth-of-burst to depth-of-crater was about two, the venting of explosion products from a row- charge detonation was less than from single-charge detonations. (auth)

This document details activities of the irradiation processing department during the month of January, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

This document details activities of the irradiation processing department during the month of October, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

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Cr{sup++} in solution produces a paramagnetic shift in the NMR absorption of 0{sup17} in C1O{sub4}{sup-}, as well as the expected paramagnetic shift for 0{sup17} in H{sub2}O. As the concentration of C1O{sub4}{sup-} increases, the shift in the H{sub2}O{sup17} absorption is diminished, and eventually changes sign. The effects are ascribed to preferential replacement by C1O{sub4}{sup-} of water molecules from the axial positions in the first coordination sphere about Gr{sup++}.