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An isochronal differential-type microcalorimeter has been designed and constructed. As a result of its simple design it is very easy to handle the samples and assemble the calorimeter. Important to the operation of the calorimeter is a program, also working on the differential principle, that provides linear temperature rise of the samples. This calorimeter is used to measure very small energy releases such as those found in precipitation, stored energy, etc. It is demonstrated that the calorimeter is easily capable of measuring 0.0005 cal with a probable error of the order of 1% to 2%.

A kinetic study of the exchange of normal and radioactive bromine in graphite-bromine lamellar compounds has been made at temperatures of 30° to 50°C. Natural and synthetic graphite powders were investigated. Two alternative mechanisms for the exchange, volume diffusion and surface exchange, were considered. The data were in better agreement with the diffusion mechanism. Diffusion coefficients of 10 -9 to 10 -8 cm2/sec and an activation energy of 11 to 14 kcal/mole were calculated for the natural graphite powders. The diffusion coefficients increased with increasing bromine content. Reversibly absorbed bromine exchanged more rapidly than irreversibly absorbed bromine.

The enzymolysis by α-chymotrypsin of the substrates, N-acetyl-L-tryptophane ethyl ester and N-acetyl-L-tyrosine ethyl ester, was followed by means of fluorescence whose intensity increased fourfold and threefold per mole respectively as substrate was transformed into amino acid. The assay by fluorescence was several orders of magnitude more sensitive than the assay by differential absorption spectra of these substances and was in agreement with it in those concentration regions where both methods overlap. To maintain linearity between concentration and fluorescence intensity, the concentration of substrate should be no greater than 10-4 M/1. In such solutions the rate of esterolysis could be followed with the enzyme at 10-11 M/1.

The main purpose of this report are to provide 1) a reference source for the interchange of analog engine model information with AGC, and 2) a reference point for future WANL analog model development. Being a model status report, the present state of the models are presents.

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Cesium Recovery from Ores. Adaptation of the phenol extraction (Phenex) process to the recovery of cesium from ore leach liquors continued to show promise. In roast-leach tests, 98 to 99% of the cesium was dissolved from pollucite ore by roasting the ore at 800 deg C with 1.8 parts of Na/sub 2/CO/sub 3/ plus 1.2 parts of NaCl and leaching with water. More than 99% of the cesium was recovered from the leach liquor and separated from other alkali metals by extracting with 4-sec-butyl-2-( alpha -methylbenzyl)phenol (BAMBP) in diisopropylbenzene and stripping with hydrochloric acid. Santophen-1 also extracted cesium effectively, but, because of the limited solubility of the cesiumSantophen-1 complex in the diluent, the utility of this phenol in ore processing is questionable. Separation of Alkali Metals. The extraction and separation of alkali metals from nitrate solutions was studied with several different types of extractants, including substituted phenols, alkylphosphoric acids, sulfonic acids, carboxylic acids, and mixtures of some of these. With all of these reagents, cesium was extracted more strongly than rubidium, which in turn was extracted more strongly than the other alkali metals. Separation factors were higher with the phenols than with the other extractants. Acid Recovery by Amine Extraction. …

A description is given of the process and equipment for the continuous conversion of plutonium nitrate to tetrafluoride powder for reduction to Pu metal. The conversion involves oxalate precipitation, filtration, calcination, and hydrofluorination. Typical results are described; the product is a free-flowing PuF/sub 4/ with a high degree of separation from impurities. (D.L.C.)

Report comparing the fuel cycle costs and temperature coefficients of reactivity for PuO2-UO2 fuel in multiple megawatt reactors.

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To evaluate the crudding characteristics of ammonium hydroxide conditioned coolant it is necessary to use a thermocouple element. The present design has accentuated structural integrity, reliability and constant heat flux. A radical departure from past designs was made by selecting a stainless steel cladding and enriched ceramic fuel. Three thermocouples are inserted in the cladding to increase the reliability. By the use of two thermocouple elements it will be possible to obtain important preliminary information on preferential crud deposition while simultaneously evaluating the crudding characteristics of ammonium hydroxide conditioned coolant.

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A road test, performed on a SNAP 10A mass mockup system, indicated that shock and vibration inputs under actual conditions were not excessive. During the course of travel from the Santa Susana field laboratory to Edwards Air Force Base, and during field trials at Santa Susana, the test system was subjected to only two accelerations exceeding 2 g, and no inputs exceeded 2.4 g. It was concluded that shock and vibration to SNAP systems from highway transporation can be adequately controlled by: selecting the appropriate vehicie, providing proper packaging; specifying route and speed limits for various driving conditions; using ordinary care in loading and unloading; and including suitable shock monitoring instruments with the shipment, (P.C.H.)

Progress in fuels and materials development is reported. Irradiation tests on powdered UAl/sub 3/ intermetallic compounds demonstrated good stability and fission gas retention capabilities. Developmental aluminum powder metal products showed good corrosion resistance at high temperatures while retaining excellent high temperature strength. All of the fuel compositions tested (UO/sub 2/, U/sub 3/O/sub 8/, and UAl/sub 3/ in aluminum matrices) exhibited density decreases under irradiation. Tensile tests on sandwich-type fuel plates at elevated temperatures indicated that the fuel plate strength is strongly influenced by the core material rather than dependent primarily on the cladding material as was found true of lower (MTR) temperatures. Three capsules containing beryllium were inserted in the ETR, in order to determine strength, gas release, and growth during a high-temperature (600--800 deg C) irradiation. An MTR fuel element employing advanced metallurgical techniques to optimize the hydraulic and heat transfer characteristics was fuily irradiated in the MTR. The fuel element consisted of 32 plates containing 250 g U/sup 235/ in a U/sub 3/O/ sub 8/--Al dispersion. A prototype ETR fuel element was made without side plates. (M.C.G.)

A transfer function for d-c operational amplifiers with generalized input and feed-back networks is derived by application of network theory. This transfer function, more general than others in common use, applies to three and four-terminal networks. It contains, as a special case, the well-known transfer function for d-c operational amplifiers with two-terminal networks. Examples are given. (auth)

A type of precision measuring instrument, a flying spot digitizer, for the analysis of bubble chamber data is described. When the flying spot encounters a bubble image, it is attenuated typically 25 to 75% depending on the directness of hit and the bubble chamber photographic and operating parameters. The width of the bell-shaped attenuation curve is approximates the sum of the spot and bubble image diameters, or 40 to 50 mu . The high precision of the FSD derives from the fact that it is possible to find the center of area of the attenuation curve to a standard deviation of 3 to 4 mu out of the much larger full-width at the base. Each flying spot coordinate is of a precision approximates equal to that given by a measuring projector, but typically 16 flying spot points are obtained to one measuring-projector point, so that the effective error is only 1/4 as large. The digital electronics problem associated with a flying spot digitizer is basically the trapping of the grating count at the time a bubble image center is found, the storage of the number temporarily until the computer is free, and then the transmission of the coordinate to the …

The cobalt and molybdenum positions had been derived from a three-dimensional Patterson function based on complete data out to λ-1 sin θMo≈ 1. From the separation of the separation of the Mo atoms it was thought that the structure contained free, unlinked MoO4 -2 ions, and this, together with the observed density and analyses for Co and Mo, suggested that the composition was probably Co2(MoO4)3. The paucity of structural information on complex oxide systems and the interesting properties, both structural and physical, of such systems prompted the present, detailed refinement of the structure. The result is more complicated and more interesting than had been anticipated: from the analysis of the X-ray data the compound is found to be NaCo2.31(MoO4)3, and this composition is consistent with chemical analyses. The structure shows several interesting features, including the partial occupancy of cobalt atoms in two independent CoO6 octahedral sites. In one arrangement of CoO6 octahedra there is the not too common face sharing to form infinite columns; in the other arrangement a zig-zag sheet, as far as we know differing from anything thus far reported, is formed by the sharing of edges and corners.

Innes, Zemen, Frenkel, Borner and Wright (1962) described an outbreak of encephalitozoönosis of the central nervous system in mice, a summary of which is given below for an understanding of why this appendix may be of interest. When the paper was presented for publication, the editors of the journal decided to omit the history of our mouse colony. In our opinion, to understand (a) how this infection may have arisen and (b) may have spread, and still exist in some colonies, it is of prime importance to know the history of this strain of mice used by us (and others). It also has lessons on the establishment and maintenance of so-called "disease-free" or "specific pathogen-free"* colonies of laboratory animals in general. Information on the history of the mice has been culled from Col. H. Yager, VC, Director of the Division of Veterinary Medicine, Walter Reed Army Institute of Medical Research, Washington, D. C., and from Drs, Clara Lynch and John B. Nelson, Rockefeller Institute, New York.

An accurate determination of the parameters of the resonance excited by the interaction of the 132 eV neutrons with the Co 59 target nucleus has been made, using the fast choppers at Brookhaven National Laboratory in the United States and Chalk River Laboratory in Canada. Neutron transmission through thick and thin samples resulted in the following parameters: [parameters not transcribed]. In addition, measurements of the resonance capture γ-ray intensity gave the value for the radiation width Γγ= 0.40 ± 0.04 eV, based on the known thermal capture cross section of cobalt of 37.5 barns. The reduced and total resonance capture integrals are calculated from the above parameters to be 50.5 ± 5.5 and 67.0 ± 5.5 barns, respectively. The above results are compared with previously determined resonance parameters and also with direct measurements of the total resonance capture integral.

The N-Reactor will be charged with tubular fuel elements consisting of two components. Both components, an outer tube with a concentric inner tube, have a uranium core, coextruded with a Zircaloy-2 cladding. The testing in support of N-Reactor fuels has been conducted in the experimental loops in the K-East Reactor. Although the process tubes in the KER loops are smaller than the proposed N-Reactor process tubes, the test loops operate at the water temperatures and pressures that will exist in the N-Reactor. To obtain the desired heat fluxes and core temperatures in KER loop test elements, enriched uranium fuel was used. The cladding surface temperatures and fuel temperatures were near anticipated N-Reactor values. Test conditions, results, and conclusions are presented.

A description of the digital readout and drive portion of the Advanced Reactivity Measurement Facility II is presented along with the philosophy used in selecting the system block diagram and components, accuracy considerations, and a preliminary evaluation of performance and usability. The presentation discourages duplicating of the equipment; advantage should be taken of the opportunity to improve upon it. To this end guideposts are provided as well as a documentation of those aspects of the design that are considered worthy of duplication. (auth)

The status of radioactive contamination of the Clinch and Tennessee River systems from Nov. 1961 to April 1962 is reviewed. Data are included from studies on the fate of radioactive materials discharged to the Clinch River by the Oak Ridge National Laboratory, the mechanisms of dispersion of radionuclides released to the river, the direct and indirect hazards of waste disposal practices during the period, an evaluation of the over-all usefulness of this river for radioactive disposal purposes, and an evaluation of long-term monitoring procedures. The management of liquid wastes at ORNL is discussed and results are reported from studies on the accumulation and movement of radionuclides in White Oak Creek basin, the contamination of river biota, hydrologic measurements and analyses, measurements of radioactivity in the river system and in community water systems downstream from the Clinch River, and calculation of estimated radiation dosages from drinking Clinch River and Tennessee River water or immersion in the water at various downstream points. Results are included from a preimpoundment study of ecological conditions of Melton Hill Lake and estimates of the effects of Melton Hill Lake and power releases from Melton Hill Dam on hydrologic conditions in the river system. (C.H.)

The information presented is a collection of most of the physics information available for the New Production Reactor. The details of some of the physics information, particularly those dealing with exposure and temperature effects, are by no means to be considered the final word since there has been no experimental verification of these effects. However, the gross physics characteristics described are felt to be reasonable representations of the expected physics behavior of N Reactor and should serve as useful guides throughout the startup planning and initial operation.