Monkeys and dogs were used in a series of studies designed to assess the ability of aurin tricarboxylic acid (ATA) to provide protection against acute beryllium poisoning. The acute LD/sub 50/ of ATA was found to be 344 mg/kg for monkeys and 164 mg/kg for dogs. Neither species exhibited significant hematological changes when given weekly ATA doses of 25 mg/kg over an 8-month period. The lethal intravenous dose of beryllium sulfate was 0.6 mg/kg for both dogs and monkeys, but the value increased to between 1 and 3 mg/kg when given by intratracheal injection. Acute toxic effects were not observed by either intravenous or intratracheal doses of suspensions of beryllium oxide. Treatment with ATA appeared to have therapeutic value in monkeys exposed to beryllium, but no significant response was observed in dogs. (auth)

A solvent extraction process was developed to produce high-purity Sr/sup 90/ from an irradiated U reprocessing waste solutlon. The extractant is D2EHPA diluted with TBP and Shell Spray Base. The process uses an acetic acid-acetate huffered aqueous phsse which is countercurrently contracted with the D2EHPA organic phase. Calcium and some Ce/sup 144/ extract with the Sr/sup 90/; extraction of other contaminants (Zr/sup 95/, Nb/sup 95/, Ru/sup 106/, and inert lead and iron) is prevented by adding either DTPA or EDTA to the feed solution. Decontamination from Ca and Ce/sup 144/ is provided by back extraction of the Sr/ sup 90/ into an aqueous 1M citric acid solution. The process was used to isolate and purify about one megacurie of Sr/sup 90/ for subsequent use in the fabrication of thermoelectric power generators as part of the Systems for Nuclear Auxiliary Power (SNAP) program. (auth)

The effect of temperature on the yield strength of the polycrystalline hexagonal Ag--Al intermetallic phase was investigated over the temperature range 77 to 775 deg K. It was found that the curve for yield stress vs temperature for both polycrystalline Ag--33 at.% Al specimens that were heavily cold-worked prior to deformation and those that were recrystallized prior to deformation was parallel to that for prismatic slip in single crystals. Increase of the percent Al in the specimens resulted in an abrupt decrease in the ductility at a composition of about 37 at.% Al. This decrease in ductility was attributed to precipitates in the grain boundaries. (auth)

The technique of radiation characterization is reviewed, with particular emphasis on new methods and their practi-cal aspects. Each type of detector is discussed in terms of its principle of operation and its applicability to various problems in counting and spectrometry. Auxiliary electronic instrumentation and the function of each instrument are described in general terms. Other topics discussed include low-level counting, absolute counting, and the mounting of radioactive sources. (137 references.) (C.H.)

The absolute differential cross sections for elastic scattering of 31- Mev He/sup 3/ ions on Be, Al, Cu, Sn/sup (nat)/, Sn/sup 120/ and Bi were measured in the angular range of approximately 10 to 120 deg in the center-of-mass system. Thin selfsupporting foil targets were chosen to span the parameter A/sup 1/3/, where A is the target mass number. The first excited states of the isotopes of these elements had sufficient energy separation from the ground state to enable elastic scattering to be resolved from inelastic scattering. The detection system, consisting of CsI(Tl) scintillation crystals, was capable of 3% pulse- height resolution and 1 degree angular resolution. Characteristically, the light- element angular distributions show strong diffraction effects. The differential cross section divided by the Rutherford cross section decreases exponentially at large angles for the heavy elements, and the differential cross sections break away from Rutherford behavior at angles which increase almost linearly with increase of atomic number of the target nucleus. A comparison of the results for natural Sn, and Sn enriched to 85% in Sn/sup 120/, indicated that within the experimental uncertainties over the measured angular interval, there were no pronounced isotopic effects. The data are presented both in …

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Inclusion of nonlinearities in the equations for phase oscillations derived for studying proton bunch behavior in the Brooknaven AGS leads to a new stable equilibrium point for the bunch not coincident with the usual stable phase angie. Equations and equilibrium point stability are examined. (D.C.W.)

Measurements of index of refraction as a function of gas pressure for carbon dioxide, ethane, methane, sulfur hexafluoride, Freon 13, Freon 14, and Freon 23, which are suitable for Cerenkov Counter use, are reported. These gases do not react with Al or Ag mirror coatings, or other materials used in such counters, and have indices of refraction that are large enough to permit the use of these gases at reasonable pressures. Methane and ethane are both toxic and highly explosive; the remainder of the group listed are non-toxic and very stable. Carbon dioxide appears to be the most suitable gas of this group for a precise determination of high energy particle velocity in a Cerenkov Counter from pressure-refractive index calibration data. Data indicate that methane and ethane have the highest dispersion of the gases of this group and Freon 23 has the lowest. Dispersion is a more serious limitation to ultimate Cerenkov counter resolution at very high energies than is muitiple scattering. In some Cerenkov Counter uses, a minimum of particle attenuation may be desirable; methane offers the smallest nuclear cross section of these gases. Carbon dioxide does not present major difficulties in attenuation or multiple scattering, and its dispersion …

The Idaho Chemical Processing Plant did not operate on fuel recovery during the period since numerous repairs and modifications were being made to the extraction and U concentration equipment, Ba/sup 140/ production continued on schedule; substantial decontamination of the RaLa facility was achieved and desirable replacement or repair of in-cell equipment was accomplished in the interval between two successive runs. Aqueous Zr fuel processing studies continued with the obje tive of adapting the HF process to continuous dissolution a complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Dissolution rates for Zircaloy-2 in 10M(bar) fluoride dissolver solution proved to be adequate for continuous dissolution (as high as 79 mg cm/sup -2/ min/sup -1/) in an acid range which resulted in both controlled gas evolution and stable dissolver solutions. Preliminary results indicate the possibility of blending Zr raffinates from this process with larger volumes of Al raffinates to achieve stable waste solutions and avoid the necessity of constructing additional special alloy tanks for Zr waste. Supplemental studies on the sodium formate process for head end precipitation of Zr snd fluoride are reported, as well as results of corrosion …

Research and development are reported in the flelds of reactor materials and components, fuel studies, UO/sub 2/ crystal growth, radiation applications, coated-particle fuels, corrosion in fluoride-volatility process, bonding processes, radiation effects on fuels, Army gas cooled reactor program and bonding of Be-clad fuel elements. (J.R.D.)

Historical developments of the ORNL dosimeter and the ORNL badge meter, Model II, are discussed. Beta-gamma and neutron dosimetry techniques are described. ORNL film dosimetry experiments are summarized. (M.C.G.)

LAMPRE I. The operations and activities carried out in conjunctnnon with LAMPRE I are summarized. Fuel and Container Development. Corrosion testing of containers made out of various tantalum alloys is described, and data are presented on the tensile properties of high-purity Ta sheet. A ternary phase diagram is presented for molten Pu-Ce-Co alloys. Melting points are given for a number of ternary U alloys and systems. A preliminary test of 5 ceramic crucibles with Pu-U-Mn fuels was made at 900 deg C. Process Research and Development. A process for reprocessing UC-PuC buttons was developed which comprises the following steps: dissolution in 13 M HNO/sub 3/-0.05 M HF, dilution, extraction of Pu and U into TBP, and selective stripping of Pu and U. A volatilization-liquatnnon run on irradiated Pu is described. A processing method was devised for recovery of U and Pu from sodium paste blankets or paste cores. Concept Development. Results of an analysis of a one-region, direct contact reactor using U -Pu fuel is given. Critical Experiments. A small-scale critical test of a circulating fuel, direct contact core called Pint Bottle Experiment is described. 2000-kw Sodium Test Facility. lts operation is described briefly. Core Test Facility. Progress on the …

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Over 30 radioisotopes were identified in the coolant of the OMRE during the period from January, l958 through August, l960. The principal gamma-emitting isotopes measured were the corrosion products: Mn/sup 56/, Fe/sup 59/ and Mn/sup 54/ the principal beta emitters were: P/sup 32/, H/sup 3/,S/sup 35/, Fe/sup 55/, and C/sup 14/. The total (gamma plus beta) activity of the coolant during normal reactor operations was estimated to have been less than l.08 mu c/gm of coolant, with Mn/sup 56/ contributing approximately 80% of the detected process radiation. (auth)

The results of studies related to the oxidation of tungsten and its alloys are presented. The pressure of WO/sub 3/ polymers over WO/sub 2/ was measured in a tungsten Knudsen cell andd found to agree with measurements in a platinum cell. Literature data for WO/sub 2/ and WO/sub 3/ were combined with vapor pressures determined to give thermodynamic values for W/sub 18/O/sub 49/and W/sub 20/O/sub 58/. Tungsten oxidation rates were measured from 800 to 1700 deg C and in pressures of oxygen between 2 x l0/sup -1/ and 10/sup -2/ atmospheres. The effects of oxygen pressure indicate that the rate may be governed by oxygen dissociating to atoms in the reacting surface. The oxidation rate is demonstrated to be independent of the oxide evaporation rate. All of the evidence indicates that if an oxide barrier layer is present at temperatures above 800 deg C it must be very thin. Studies on the oxidation of tantalum tungsten alloys between 800 and l200 deg C indicate that the 50-50 alloy has the greatest oxidation resistance, oxidizing at a rate as much as l0 times slower than tungsten alone. (auth)

Tables of electronic radial functions are presented. The finite nuclear size effects and the finite deBroglie wave length effects were incorporated in this work. A brief summary of the formulation of the problem is given. (M.C.G.)

An analysis of the transient behavior of a 255-Mw(e) advanced sodium graphite reactor, previously described in NAA-SR-3829, is presented. The reactor and its components are briefly described. Nuclear and thermal characteristics are presented as far as they affect reactor kinetics or are essential in interpreting the results. The study includes an investigation of the inherent kinetic characteristics of the reactor, as well as and analysis of its transient behavior for all conceivable conditions of abnormal operations. Assumed reactor excursions are analyzed with and without ensuing protective system action. It is shown that the reactor is dynamically stable and that power transients which are followed by normal protective system actions will not lead to potentially unsafe conditions. The conclusion is reached furthermore, that uncontrolled rod withdrawal accidents from source power will be terminated by coolant choking'' and fuel meltdown before extensive coolant boiling occurs, and that the large thermal capacity and long-time constant of the upper plenum will provide protection against pool boiling for other less serious accidents until the reactor can be shut down by external means. (auth)

Zirconiurn alloys used in the fabrication of nuclear fuel elements can be disintegrated and converted to insoluble oxides by electrolytic treatment in concentrated nitrate solutions. This reaction shows promise as a technique for reprocessing nuclear fuels clad with Zircaloy-2. For a particular applied voltage, nitric acid achieves the highest rate of attack, but the reaction can be carried out at rates of 2 mg/(cm/sup 2/)(min) or greater in either 7.5M sodium nitrate or 2.3M aluminum nitrate. A reaction rate of 7 mg/(cm/sup 2/) (min) can be easily attained in either 8M nitric acid or 7.5M sodium nitrate. The rate of reaction is a function of the temperature and tho applied voltage. An as-yet unsolved problem is the carry--down of uranium with the insoluble zirconium oxide product. (auth)

Isothermal reaction curves and T-T-T curves showing the effect of different variables on the beta-alpha transformations in plutonium are presented. Impurity content, stresses, beta heat-treating time and temperature, hydrostatic pressing, specimen size, and thermal cycling influenced the kinetics of the beta- alpha transformation. Decreasing the impurlty content increased the rate of transformation. High tensile stress retarded the beta-alpha transformation. Increasing the beta heat-treating time and temperature markedly decreased the rate of transformation. Hydrostatic pressing at 90,000 psi accelerated the beta- alpha transformation under pressure but decreased any subsequent beta-alpha transformations by as much as two orders of magnitude. Specimen size had no effect on the start of the transformation but increasing the specimen size from 0.010 to 0.37 inch decreased the rate of completion of transformation several orders of magnitude. Thermal cycling less than 15 cycles did not affect the rate of transformation. The density of high purity plutonium during hydrostatic pressing at l80 deg C and cooling under pressure increased from 19.60 to 19.65 g/ cm/sup 3/to 19.70 to 19.75 g/cm/sup 3/. This increase was shown to be attributed to decreasing the volume of microcracks rather than transformation of any metastable beta phase. A T-T-T curve of the alpha-beta …

The nuclear characteristics of a variety of small reactors composed of thoria -urania fuel in heavy water were determined in a program of critical experimentation. The fuel element consisted of ceramic ThO/sub 2/-U/sup 235/ O/ sub 2/ pellets stacked to a height of 1.5 m within 0.787-cm-OD aluminum tubing. The pellets used most frequently were of 0.587-cm diameter and had a Th/U/sup 235/ atom ratio of 25. Rods containing similar pellets with only half as much U/sup 235/ were used to achieve small changes in the U/sup 235/ content of the cores. Some cores were assembled with 0.660-cm-diameter pellets having an atom ratio of 15. All cores were located in a 2-m-diameter tank containing D/sub 2/O. Three distinct core structures were used, allowing measurements with uniformly distributed fuel rods, loading patterns compatible with the EBWR core geometry, and clustered lattic arrangements with D/sub 2/O, H/sub 2/O, and air surrounding the clustered fuel. Most of the cores assembled had some amount of radial D/sub 2/O reflector. A 0.3-m-thick bottom reflector composed of D/sub 2/O and aluminum was always present. For most of the assemblies, the control rods were fully withdrawn, criticality being achieved by adjustment of the water level. Observed critical …

This document details the activities of the Irradiation Processing Department during the month of November 1961.

A 500 MWe sodium-cooled, PuO2-UO2 fuel, fast spectrum reactor design is presented, which is calculated to have a fuel cycle cost in the civinity of 1 mill/ekw hr, and to have important safety features due to an appreciably negative Doppler effect.

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