Uranium-aluminum compounds were prepared by solidsolid reaction of aluminum powder and uranium hydride; x-ray-diffraction patterns showed that single phases of UAl/sub 2/, UAl/sub 3/, and UAl/sub 4/ could be achieved. The uranium-beryllium compound, UBe/sub 1//sub 3/, was prepared by solid-solid reaction of berylllum powder and uranium hydride. The uranium-boron compounds, UB/sub 2/ UB/sub 4/, and UB/sub 1//sub 2/ were prepared by solid reaction, and single borides were obtained; carbon contamination was especially serious in these samples. The uranium-carbon compounds, UC and UC/sub 2/, were prepared by solid-solid reactlons to 1200 deg C; the x-ray-diffraction patterns showed a mixture of phases, and higher temperatures are probably required. The uranium- nitrogen compounds, UN and UN/sub 2/, were prepared by reaction of uranium with ammonia at 850 deg C for UN/sub 2/ and subsequent heating of that product in vacuum for UN. The uranium-selenium compounds, USe and USe/sub 2/, were prepared in very small samples; the violence of the reaction of selenium with uranium hydride and the lack of availability of hydrogen selenide limits the size of preparations. The uranium-silicon samples, USi/sub 2/ and USi/sub 3/ were prepared by solid-solid reaction of UH/sub 3/ and 8i; numerous attempts were made to prepare U8i. …

This report discusses benefits in an increase in the flow of water from the lower depths of the Grand Coulee Dam which was used to lower river temperature at HAPO. A net average daily reduction of over 1.2{degree}C resulted at HAPO with a peak of 2.7{degree}C. The Net Production gain from temperature change was 6910 MWD and the Cost of Control was: Grand Coulee Charges $3,120.00, and other (Estimated) 6,880.00 for a total of $10,00.00.

Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.

The means used to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redssign of system components to utilize alteraate coolants such as nitrogen, air, and NaK. The use of kerosene to replace tetralin, where double containment is provided, is discussed. The physical properties are compared, and kerosene is shown to be free of the undesirable characteristics of tetralin. The fuelelement cleaning systsm was redesigned for steam washing, followed by a water rinse and vacuum drying. Hydrogen gas evolved during washing is oxidized with copper oxide to eliminate the possibility of a hydrogen-oxygen explosion if air should accidentally enter the vent system. The fuel element was changed from a seven- to a five-rod cluster to provide additional clearance in the channel. Element hardware was modified to provide an orifice location which will permit more precise flow calculations; a redesigned hanger assembly which will minimize sodium holdup; and filter screene at the channel entrance to prevent in-cluster plugging. Diagnostic instrumentation was provided for the reactor to monitor: fission-product activity in the reactor cover gas; rapidly varying reactor parameters during a reactor scram; internnl and aheath fuel temperatures; and fuinctions being performed …

The objectives of this test are: 1. To establish grain size limits for acceptable uranium fuel element cores. 2. To establish, if possible, criteria for predicting core dimensional stability during irradiation by comparing the relative dimensional stabilities associated with grain size and with variations in grain size in individual cores. 3. To obtain process tube and fuel corrosion data associated with bumper fuel elements in new tubes with no mixer, one mixer in the 10th position and two mixers in the 7th and 15th position from the rear. Fuel cores representing the full range of UT-2 voltage values (grain size converts to d-c voltage) of interest are segregated into three categories: a. Large grains. b. Variations of grain size in an individual core. c. Small grains. Each category will be subdivided into three groups, each covering a small range of values. After canning, the finished fuel elements will be assembled into twenty-seven (27) charges in three latin square patterns for irradiation to a 900 MWD/T exposure goal in D Reactor.

The evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam in a sodium-heated Type 316 stainless steel steam generator is reported. The purpose of the coating is to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It is concluded that the Kanigen coating does not afford adequate protection for the service conditions. (D.L.C.)

Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the research and development program for the United States Atomic Energy Commission sodium Components Design Project.

This document reports progress during the month of February, 1961, recording investigations and studies of a flow rate using a curved pipe or S-tube and documenting measurements of mass flow, tube design and construction.

Machining was completed on the s-tube flow element, and a spring, for use at a constant known temperature, was constructed for the flow element. Calculations for geometry factor, detector efficiency, and effective absorption along the useful radiation path were completed for the reed densitometer. The flow rate control was calibrated and performed satisfactorily. Response to step transient changes occurred with a damping constant of about 0.6 and an effective response time of 10 sec. Sources of error in the s-tube flow rate measurements are discussed. (M.C.G.)

This is the monthly report for the Hanford Laboratories Operation, January 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This document details activities of the irradiation processing department during the month of January, 1961. 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; Employee Relations Operation; Financial Operation; and NPR Project.

A theoretical treatment is made of the stress-strain and plastic flow properties of spherical shells of stainless steel under dynamic loading. The results are used to calculate the response of a homogeneous reactor core to inential pressure pulses. The importance of the duration of the pressure pulse as compared with a natural time or period of the material in plastic as well as in elastic deformation is noted. For a small homogeneous reactor core vessel, the natural plastic "swing time" is found to be about 0.25 msec. The rise time of the pressure pulse is 2.5 msec while the decay time is approximately 12.5 msec. Thus the rise time of the pressure pulse is about 10 times as large as the ""swing time,'' which means the static pressure approximations hold quite well, and maximum energy absorption is determined for the conditions under which the vessel will fail. (auth)

A calculation of the three-group flux distribution of the initial wet critical loading of KW reactor was made using the same calculation techniques as those employed in NPR three-group calculations. The calculation results are directly comparable to experimental data obtained during the KW loading. The calculated radial geometrical buckling of the critical loading is 48.2 {mu}b compared to a measured value of 49.8 {mu}b; these agree within estimated experimental error. The calculated reflector augmentation distance is 54.5 cm compared with a measured value of 49.2 cm. The three-group nuclear constants of the KW lattice components were calculated from 18-group data (APEX-515) based on the flux spectrum of HW-63172. A cell calculation was made to determine the effective constants for the homogenized cell. The calculated k {infinity} of this cell came out 0.998 compared to a measured 1.034. Since the resonance capture of U-238 is difficult to treat, in three-group theory, all error was assumed to be in this parameter which was adjusted accordingly to give k {infinity} = 1.034. The resulting core parameters are given in Table I, along with parameters for the dry, unloaded core and the wet unloaded core.

A hydraulic analysis of the Pathfinder boiler core was completed. A description of flow paths including a schematic diagram is included. Pressure drops along primary and leakage fiow paths were calculatsd. After the resistance of each of the leakage paths was identified and the available driving forces in terms of pressure drops associated with the active fiow were established, the leakage rates were easily determined. The dependence of pressure drops on core operating parameters was investigated. The boiler flow rates were also determined. The natural circulation flow rate as a function of power level was estimated at normal condltions of temperature and pressure. The relationships between the boiler parameters of fiow, power, pressure, and inlet subcooling which arise through the laws of conservation of mass and energy are presented. (M.C.G.)

The flux of hydrogen gas through Hastelloy B, hot forged to 20% reduction was determined as a function of membrane thickness, pressure differential, and temperature. The experimental data were fitted to the equation J = (1810 P/sup 1/2//X exp (-8422/T) where J is the flux (cc at STP/ (cm/sup 2/- hr)); P is the pressure (atmospheres); X is the membrane thickness (mm); and T is the temperature ( deg K). (auth)

Modifications of EBWR are described, and data from analysis of control- rod operational crud deposit are tabulated. Development and construction progress on Borax V are summarized. Research for ZPR III is reported on a series of uranium oxide critical cores. Comparative data on composition, critical masses, and central fission ratios are tabulated for these assemblies. Developmental work on ZPR-VI, ZPR-IX, and Juggernaut is summarized, followed by a summary of EBR-I operation and development of EBR-II. Studies of reactor steam superheating concepts are reported from which conclusions are listed. In reactor safety studies, data were obtained on the extent of water reaction with various metal combinations for use in cores as function of energy input. In other work in-pile melt down studies were conducted. Operation and development of TREAT are described. Nuclear technological developments are summarized in sections on physics, fuel development, reactor components and materials, separations development, and advanced reactor development. (For preceding period see ANL- 6295.) (J.R.D.)

"This is the third quarterly report on Task II dealing with Methods Development for Radio-Tracing of Coal Product Hydrocarbons With Tritium. The problem of accurate low-level tritium assay for tagged hydrocarbons has been resolved and attention is now primarily directed at the questions of tritium mobility and radio-chemical purity in tagged tracers."

"Adlam and Allen and Davis, Lust, and Schluter have studied nonlinear plane-waves, propagating normal to the magnetic field, in a cold plasma. One solution of particular interest is a solitary wave, or single pulse. We present a method for solving the analogous problem for a plasma with finite temperature, in the limiting case where the amplitude of the wave is small and where, consequently, the width of the waver is very large."

A new model of the higher symmetry of elementary particles is introduced ln which the eight known baryons are treated as a supermultiplet, degenerate in the limit of unitary symmetry but split into isotopic spin multiplets by a symmetry-breaking term. The symmetry violation is sscribed phenomenologically to the mass differences. The baryons correspond to an eight-dimensional irreducible representation of the unitary group. The pion and K meson fit into a similar set of eight particles along with a predicted pseudoscalar meson X/sup o/ having I = 0. A ninth vector meson coupled to the baryon current can be accomodated natarally in the scheme. It is predicted that the eight baryons should all have the same spin and parity and that pseudoscalar and vector mesons should form octets with possible additional singlets. The mathematics of the unitary group is described by considering three fictitious leptons, nu , e/sup -/ , and mu /sup -/, which may throw light on the structure of weak interactions. (D. L.C.)

This is the monthly report for the Hanford Laboratories Operation, February 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

Both in magnetohydrodynamic shocks and in accelerated partially ionized gas flow across a magnetic field, space charge separation occurs that establishes very large electric fields in the direction of motion. The width of the current layers associated with the acceleration is never less than the electron Larmor radius with no collisions and is broadened by electron collisions to a width solely determined by the effective resistivity. The electrons gain an energy regardless of collisions equal to the electric potential difference across the layer. This potential corresponds to the change in kinetic energy of mass motion per ion. For slightly ionized gases, the additional stress of neutral ion collisions within the layer can make the electric potential and hence gain in electron energy very large for only modest changes in mass velocity. Hence ionization may occur when the change in kinetic energy of the ions is small compared to the ionization potential.

Design, development, and testing efforts were continued on BORAX-V, EBR- I, EBR-II, EBWR, JUGGERNAUT ZPRIII, ZPR-VI, and ZPR-W. An evaluation program is outlined for Pebble Bed Reactor designs. Fast and thermal reactor safety studies were conducted. Experimental and theoretical studies in applied nuclear and reactor physics are dsscribed. Developments made in reactor components, fuels, and materials are discussed. Heat engineering studies were conducted on steam separation, and velocity and void distributions in two-phase systems. Fluidization and fluoride volatility separation, and chemical-metallurgical separation processes were studied. Advanced reactor concepts that were discusssd includsed. Basic Radiation Effects Beactor, Biogeonuclear Reactor, Fast Reactor Test Facility, compact high-power density fast reactors, AHFR hydraulic test loop, Packed Bed Reactor, and direct conversion. (For preceding period see ANL- 6328.) (B.O.G.)

Results are summarized for a survey of methods for predicting fuel element and coolant behavior in sodiumcooled fast reactors under abnormal operating conditions. Circumstances prior to, during, and after meltdown are considered, and the behavior of fuel and coolant during transients is discussed. Reactor excursions, theory of fuel element thermal transients, reactor coolant transients in single and two-phase flows, and specific topics such as two-phase flow patterns, two-phase pressure drop, and transient voids in boiling coolant reactors are also treated. Some applicable mathematical treatments are given along with an annotated bibliography. (D.L.C.)

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