From Preface: "A brief description of the method used in compiling these tables and the limitation of coverage is given in the preface to Supplement 1. A description of the numbering system used is classifying reactions for the tables is given in Supplement 2. The present supplement contains information pertaining to Substitution, Exchange and Elimination reaction types. It is not complete as still more material falling groups is being prepared."

Report issued by the APDA over a design study "of a facility for testing sodium-cooled thermal reactor fuel assemblies in the Advanced Test Reactor" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.

The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.

Abstract: The design and application of two computers for the HNPF protective system is discussed.

Abstract: This report describes the fabrication of elements for the OMRE third core loading.

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.

Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.

Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.

From abstract: This report describes a conceptual design and economic evaluation of 300 and 40 MWe steam-cooled fast breeder reactor power plants performed by NDA under contract with the AEC.

Abstract: Zircaloy-2 weld metal, obtained by inert gas non-consumable-electrode welding, was subjected to tensile, strain fatigue, and creep-rupture testing.

For the purpose of evaluating the compatibility of graphite and INOR-8 in a dynamic fluoride fuel medium, INOR-8 Forced Convection Loop No. 9354-5 was operated 8850 hr. The loop operated at maximum temperature of 1300 deg F and circulated a fluoride fuel of the system LiF--BeF/sub 2/-- UF/sub 4/. Post-test examinations of the graphite and loop components revealed no apparent corrosion or carburization problems. (auth)

As part of a general hazard review survey conducted by the Chemical Technology Division of its facilities, transient pressures due to impulse and ramp perturbations to the cell ventilating systems of buildings 3019, 3026, and 4607 and the closed glove box system of 3508 were calculated. From the portions of the pressure curves above atmospheric pressure, volumes of gas outleakage were estimated; thus the amount of activity released can be calculated if an estimate of the activity concentration is available. The volumes of outleakage for all four ventilating systems were small for reasonable sizes of perturbations. For an impulse perturbation causing an instantaneous rise of +8.0 in- H/sub 2/0, the length of time above atmospheric pressure and estimated outleakages for PRFP cells in 3019 are 1.5 sec and 3.1 ft/sup 3/, respectively; for volatility cell 1 in 3019, 0.33 sec and 0.45 ft3; for cell A in 3026, 2.1 sec and 3.0 ft/sup 3/; for a glove box in 3508, 0.066 sec and 0.04 ft/sup 3/; and a cell in 4507, 0.26 sec and 0.03 ft/sup 3/. (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.)

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.)

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.)

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. …

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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.)

General research and development on water-cooled and sodium-cooled reactors are reported along with specific developments on EBWR, BORAK-V, EBR-I, and EBR-H. Thermal and fast reactor safety studies are summarized in terms of fuel-coolant chemical reactions, kinetics of oxidation and ignition of reactor materials, core meltdown studies, and a sodium vapor pressure furnace. Evaluations were made of improved fast reactors for central station power and of a 50-Mwe Prototype Organic Power Reactor (POPR). Developments in instruments, reactcr fuels and materials, reactor components, heat engineering, separations processes, and advanced reactcrs are discussed. (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)

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)

Short-term corrosion tests with types 1100, 5154, 6061, and X8001 aluminum alloys were conducted in water at flow rates rsnging between 20 and 107 fps and at temperatures between 170 and 290 deg C. Corrosion of the alloys was less dependent on flow rate in the range of 20 to 67 fps than at higher velocities. At temperatures as high as 230 deg C no evidence of localized attack, except for random shallow pitting, was exhibited by these alloys, and all had comparable corrosion rates. At 260 and 290 deg C all alloys except X8001 showed extensive subsurface attack. At 260 deg C and at velocities up to 67 fps, the corrosion rate of X8001 aluminum was high during the early part of a run and then decreased to rates of between 5 and 15 mpy; at the highest velocity, the corrosion rate was constant at 200 mpy. Tests with X8001 aluminum at 260 deg C showed that mechanically polished specimens corroded at about the same rate as those with a machine finish. A significsnt improvement in corrosion resistsnce at 20 to 67 fps was accomplished, however, by exposing the specimens to water at 250 or 300 deg C in …

WHIRLAWAY is an IBM 7090 FORTRAN programmed code for the solution of two- group neutron diffusion equations in xyz geometry. The code was designed to run under control of the IBM 7090 FORTRAN Monitor System on a machine with at least six tape units. The maximum number of mesh points is limited to 12,750. Arbitrary distributions of materials and mesh spacing are permitted. The boundary conditions are either zero flux or zero current at each of the six faces of the reactor, and the code will, if desired, compute the adjoint-flux and associated flux-adjoint-flux region integrals that are necessary for perturbation calculations. Computation time is approximately 0.006 sec per point iteration. Normally, running times are about 2 to 3 hr for a 10,000-point problem. (auth)

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 …