The percentage of helium which will bypass the core if the reflector system shown is used is predicted. It is estimated that nominally about 0.1 to 0.2% of the total flow will bypass the core, which is not considered excessive. The most difficult parameter to determine was Z, the gap between the sealing surfaces. The method used to predict Z is presented. The effect of bowing due to a temperature gradient across the seals is discussed. (auth)

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.

A graphical compilation is presented of atomic and molecular cross sections of interest to controlled thermonuclear research. The cross sections are shown, as a function of energy, for collision processes involving molecular ion dissociation, charge exchange, excitation, ionization, photoionization, scattering, energy loss, and recombination. Pertinent nuclear cross sections are also included. A bibliography is given covering the literature since 1950. (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)

ICPP Operations. Changes made in processing equipment are described, and the use of continuous steam stripping to free waste solvent of Pu is described. Agueous Processing Studies. Studies were made of methods for separating Zr from dissolver solutions of U-Zr alloys. Recovery of U from BeO/ sub 2/-UO/sub 2/ ceramic fuels by grinding-leaching technique using boiling HNO/ sub 3/ reached 75 to 80%. Waste Calcination. Test results of feed spray nozzles for use in the Demonstrational Waste Calcining Facility are given. Studies were made on the calcination of aluminum nitrate and zirconium fluoride waste solutions. Waste Treatment. Removal of Cs and Sr from wastes by adsorption was investigated. The conditions for optimum separation of Fe, Ni, and Cr by Hg cathode electrolysis from waste solutions resulting from processing of stainless steel reactor fuels were determined. Electrolytic Dissolution Systems. The electrolytic dissolution of type 304 stainless steel was studied in the transpassive region as a function of electrode potential and HNO/sub 3/ concentration. An analog simulation study of an electrolytic dissolver is described. A niobium cathode in an electrolytic dissolver dissolving stainless steel in boiling HNO/sub 3/ did not absorb H/sub 2/. The corrosion resistance of several container materials to 1 …

Programming a computer that optimizes the beam in the Brookhaven AGS is discussed. Layout, method, and routines are given particular attention, and representative data cards are shown. (D.C.W.)

A conceptual design and economic evaluation of 300 and 40 MW/.sub e/ steam-cooled fast breeder reactor power plants were performed. A reactor core composed of U-Pu oxide rod-type fuel elements clad with Inconel-X and surrounded by a blanket of depleted UO/sub 2/ fuel was studied in some detail. Reactor breeding ratios of from 1.27 to 1.5 and overall system doubling times of from 20 to 30 years are achievable. For the near term (1967) 300 MW/sub e/ plant, an energy cost of 7.6 mills/kwh is estimated, based on AEC ground rules for privately financed plants and utilities. This cost may go down to 5.7 mills/kwh by 1975. For the 40 MW/sub e/ plant corresponding energy costs are 19.5 and 13.7 mills/kwh, r -spectively. The R&D program required for this reactor concept is estimated at million with an additional million for improvements leading to the 1975 reactor. Investigation of the operational and safety aspects of the reactor indicated that satisfactory procedures can be used for startup, shutdown, and emergency cooling of the reactor. An increase in reactivity upon flooding can be prevented by incorprating small amounts of high resonance absorption material in the core. Preliminary calculations indicate a substantial increase in …

Studies carried out on corrosion associated with the hydrofluorination- dissolution phase in the fused-salt Fluoride Volatility Process are summarized. Corrosion for hydrofluorination-dissolver vessels used in bench-scale and semiworks-scale process development at ORNL is discussed. The results of a study on construction materials for the dissolution phase are presented. Corrosion studies at ANL are described for comparison purposes. A full-size hydrofluorinator dissolver is described. (M.C.G.)

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 …

This document presents the total control aspects of the current blanket and central zone E-N loading at H Reactor based on the calculational parameters in Physics of E-N Load compared to Natural Uranium Load at H Reactor, D.I. Monnie, May 11, 1961. The original charge for the E-N core load at H Reactor, (19.37 in. E to 1 in. N) was found to be more reactive than desirable for maximum production efficiency. Therefore a less reactive E to N ratio (18.14 in. E to 1 in. N) has now replaced the original loading.

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 mechanisms and kinetics of the loss of boron during heating at 1135 deg C under various dynamic environments were determined from powder compacts of 5 wt% elemental boron dispersed in matrices of Fe, Cr, Ni, Si, Fe/sub 2/O/sub 3/, Cr/sub 2/O/sub 3/, NiO, and SiO/sub 2/, compacts of austenitic stainless steel alloy powder containing 0.25 wt% boron, and wrought specimens of 0.13 wt% boron-- stainless steel alloy. The compacts containing 5 wt% boron were heat treated in vacuum, highpurity argon, wet helium, and hydrogen. With the exception of those heat treated in hydrogen, significant boron losses occurred only when a supply of oxygen, either from the sample itself or as a deliberate addition to the heat- treating environment, was available. Correspondingly, the loss mechanism is postulated to be the oxidation of boron to boron sesquioxide and its volatilization from the sample. The loss rate is controlled by the volatilization rate of the oxide which is directly influenced by structure of the compact and sintering environment. Independent of the chemical nature of the matrix, boron losses were incurred during heat treatment in hydrogen. Variations of the water content of the hydrogen from 7 to 460 ppm did not significantly influence …

Under the influence of radiation, the coolant-moderator in an organic moderated reactor slowly decomposes to form high molecular weight polymers (high boilers) and a mixture of gases and light hydrocarbons as waste products. Work carried out on the improvement and subsequent operation of a prototype waste- polymer combustion process is described. Operation of the improved unit employing a vortex'' burner confirmed the feasibility of combustion as a disposal method. It was determined that fuel temperatures of 400 deg F and combustion air temperatures of 300 deg F were required for successful operation. The quantity of ash resulting from the combustion was established to be less than 0.5 wt% of the original polymer. It was determined that the efficiency of the primary dust collector varied from approximately 90 to 99%, and that there was no detectable particulate matter in the gas leaving the absolute filter. Attempted activity-balance calculations proved unsuccessful due to extreme difficulties in measurement of the low-level activty of the stack gas. In an effort to further improve and simplify the process system, preliminary evaluation of another burner was carried out. A cost estimate of the combustion process using the Vortex'' burner was prepared, based on data obtained from …

Laboratory and pilot plant work directed toward development of decontamination methods for high-temperature pressurized water systems are deseribed. It is noted that failure and corrosion of metallic U fuel elements in such systems produces uranium oxides wofth a large percentage of fission products remaining assoeiated with the oxide particles. Decontamination requires dissolution and/or flushing of these oxides from the system. A summary of spceific tests involving promising solutions is presented. (J.R.D.)

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.)

The electrical resistivities of polycrystalline samples of La, Pr, Nd, and Sm are reported in the temperature range 1.3 to 300 deg K. La exhibits a superconducting transition at 5.8 deg K. The curve for Pr has slope changes at 61 and 95 deg K. The Nd curve shows small jumps at 5 and 20 deg K. Sm shows slope changes at 14 and 106 deg K. (auth)

A review of the theories of electron paramagnetic resonance in biology is presented, including a discussion of the nature of the physical observation, followed by examples of materials of biological interest. Iq discussing these examples, information is presented in terms of the nature of the starting material under observation rather than the nature of the magnetic entities observed. The examples proceed from the simpler molecules of biological interest (metabolites, vitamins, cofactors) into the more complex materials (polymers, proteins, nucleic acids) toward cellular organelles (mitochondria, chloroplasts) and, finally, to whole cells, organisms and organs. The observation of photoinduced unpaired electrons in photosynthetic material is described and the various parameters controlling it are discussed. The basic observation is interpreted in terms of a primary photophysical act of quantum conversion.

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.)

The interaction Hamiltonian for the Coulomb exchange effect between conduction electrons and magnetic-shell electrons in rare-earth metals was derived from first principles. The approximations under which the interaction can be represented by the product of electron and ion spin vectors are exhibited. (auth)

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 report details activities of the Fuels Development Operation for the months of April, May, and June 1961.

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 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.