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The Stationary Low Power Reactor No. 1 is a three Mw boiling water reactor designed to demonstrate the feasibility of a nuclear reactor to supply electrical power and space heat for remote sites. In addition to performance evaluation the facility provides training for military personnel. The reactor was operated for 1159 hr during the quarter for a total core burnup of 20.3%. Power generation was 103.7 Mwd for a total power accumulation of 466.9 Mwd. Eight malfunctions occurred during the quarter for a total unscheduled downtime of 40 hr 44 min, As a result of malfunctions, aluminum keys will be installed on the control rod drives, instrument well covers were removed, and an order has been placed for a station auxiliaries breaker with a higher temperature rating. Data were taken on seven tests during the quarter. Four of these are expected to be completed during the next quarter. All equipment items on order for the SL-1 power extrapolation expansion program are scheduled to be delivered before June 15, 1960. Although condenser dampers and damper controls, process instrumentation, equipment cabinets, and the radiation monitoring equipment have not yet been ordered, construction will not be delayed. The two tie-ins to the existing …

The concentrations of and activities due to N/sup 16/ and N/sup 17/ in the HFIR primary coolant water were calculated. At the pressure vessel exit, the N/sup 16/ activity is 3.9 x 10/sup 6/ dis/secml and the N/sup 17/ activity is 6.9 x 10/sup 2/ dis/sec-ml. Comparison of the N/sup 16/ activity with the data obtained from the ORR water system indicates that the calculated results are slightly conservative. (auth)

Recently there has been a great surge of interest in almost-exact sum rules for the magnetic moments of nucleons. (By almost-exact we mean: exact to all orders in the strong couplings but only the lowest order in electromagnetic and weak couplings.) Besides providing a means for calculation of the magnetic moments on the same level as the calculation of GA/GV by Adler and Weisberger these sum rules, taken together with the Adler-Weisberger sum rule, constitute a useful tool for investigating the nature of the dynamical approximations that underlie higher symmetry schemes.

Uniform, dense coatings of alumina about 5 to 150 mu thick were applied to uranium dioxide particles 44 to 350 mu in diameter by hydrolysis of aluminum chloride vapor in a fluidized bed of the particles at 1830 deg F. The coated particles were resistant to nitric acid leaching, to oxidation in 1830 deg F air, and to thermal cycling from 6OO to 2500 deg F. After low neutron exposures, the coated particles showed excellent fission-gas retention at temperatures up to 2400 deg F in inert gas. Although not optimized in the study, the coating process appears to have commercial feasibility. (auth)

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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.)

The role of the marrow as a site for antibody formation has been considered for many years. In 1912 Ludke reported the appearance of antibody in cultures of marrow cells obtained from previously immunized rabbits. Specific agglutinins for killed typhoid bacilli and lysins for ox red cells and sheep red cells were detected in the culture media 2 to 5 days later. However, the cultured cells failed to produce antibody when these antigens were added to the media. Similar findings by Reiter, Przygode, and Schilf appeared in the early literature with regard to the appearance of antibodies to various antigens in tissue cultures of bone marrow from immunized animals, along with failure to elicit antibody formation by addition of antigen to the culture resulted from the addition of excess amounts of antigen, so that if antibody synthesis occurred, the excess antigen combined with antibody and significant amounts of free antibody could not be detected in the culture media. Thorbecke and Keuning observed an increase in antibody in culture fluids when bone marrow fragments from rabbits immunized to paratyphoid B vaccine were cultured in roller tubes.

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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)

Abstract: Progress is reported on research and development tasks under the Program Plan for Engineering Support and Development of Army Pressurized Water Reactor Power Plants, Contract AT(30-1)-2639, during the six months' period October 1, 1061 to March 31, 1962.

Concrete mix design criteria, based on existing theories of proportioning and specifically oriented toward the solution of radiation shielding problems, were developed. Effects of aggregate gradation, cement-to- aggregate ratio, and water content were examined. A barytes concrete, designed according to these criteria, was thoroughly investigated in the Lid Tank Shielding Facility. Relative effectivenesses of dry aggregates, aggregates plus cement, and cured concrete were compared through thermal-neutron flux, fast- neutron dose, and gamma-ray dose measurements behind slab configurations. Attenuation was measured for the aggregate, the aggregate plus cement, and for the barytes concrete. Comparison with attenuations calculated on the basis of removal cross sections for the measured chemical compositions showed satisfactory agreement. (auth)

Lengths of pistillate inflorescences of sedges (Carex spp.) growing in the contaminated soils of White Oak Lake bed were measured in relation to radiation fields. Carex Frankii Kunth and Carex vulpinoidea Michx. populations were sampled from areas with air dose rates of 0, 10, 20, and 40 mr/hr. Analyses of variance showed that mean lengths of inflorescences of C. vulpinoidea were simllar to each other in these areas but that those of C. Frankii were significantly different. However, the sites differ in such factors as soil moisture, fertility, and alkalinity, so that these differences in the length of inflorescence may not be accounted for primarily by the exposure dose rate of the radiation field. (auth)

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.

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Temperatures were calculated relative to the storage of radioactive solid waste as a function of time and radial distance for radioactive solid cylinders in infinite solid media of "average soil," "average rock," and salt. A resistance at the cylinder--infinite medium boundary was included in the form of an air space. For the range of parameters used and withia the practical limits of accuracy, the maximum temperature rise increased linearly with the heat generation rate. The fission product spectrum was not significant in the determination of the maximum temperature rise. Under the pessimistic storage conditions assumed, the storage of cylinders of a practical size appears feasible without excessive temperature rise. A maximum temperature rise of 1000 deg F would be produced with an initial heat generation rate of 1300 to 1600 Btu/hr-ft/ sup 3/ for cylinders with a 5-in. radius, with 350 to 450 Btu/hr-ft/sup 3/ for a 10-in. radius, and with 175 to 210 Btu/hr-ft/sup 3/ for a 15-in. radius, assuming a thermal conductivity of the radioactive cylinder of 0. 1 Btu/hr-ft- deg F. (auth)

From abstract: The Madelung constant and the inverse twelfth power repulsion factor have been calculated for the wurtzite structure for wide ranges of the crystal parameters and u.

To provide the NERVA test program with a temperature measurement system of sufficient accuracy to satify present and future requirements, a cryogenic temperature measuring system was designed and developed employing a platinum resistance thermometer (RTT) as the sensor.

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. …

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From Introduction: "This Monograph has as its purpose the compilation and analysis of the extensive radio refractive index data available within the Central Radio Propagation Laboratory of the National Bureau of Standards. This will be accomplished by presenting both tabulations of basic data for specific locations and charts for interpolation to any location."

It has been observed that energetic gaseous ions mark their region of impingement on certain metals in color. Under identical conditions of bombardment, multicharged ions of the same gas mark their impact areas with different colors. The colors are sensitive to the type and energy of the ion as well as to the metal bombarded. These colors may result from reflections from thin films formed by reactions at the target. Because the colors indicate that thicker films are produced with increased ion energy, ion penetration depth as predicted by theory is compared with the depth indicated by the colors observed.

"This report presents the conceptual design of a 75 MWe prototype Mixed Spectrum Superheater power plant. The scope of the work has emphasized primarily the design, performance, and cost information on the nuclear portion of the plant. The research and development programs required to insure plant feasibility are also present."--Intro.