"The study of the toxicity of Ra and MsTh(Ra/sup 228/) in humans was continued. Several Thorotrast cases were also examined. Physical and clinical studies were made on 151 persons. In all cases possible gamma ray measurements were made of Ra and MsTh decay products retained in the body, alpha -ray measurements of Rn and Rn/sup 220/ in breath, a complete medical history was taken, a complete x-ray examination was made of the skeleton, and urinalysis, hematological, and blood chemistry studies were made."

None

"Progress is reported on: design of a continuous flow system for the irradiation of silane using a Cos5 source; pile irradiation of silane samples at elevated temperatures; investigation of materials other than silane, including nonsilicon compounds as well as those containing the silyl group; modification of the existing vacuum system for handling larger quantities of silane as well as increasing the accuracy of the pressure measurements; and use of an electric discharge for the decomposition of silane. The work performed during the period of this report consisted of the following: 1. Preparation of silane and filling of sample containers for Co60 and in pile irradiation studies and thermal decomposition studies, 2. Construction of various heaters to be employed for the thermal decomposition and high temperature irradiation studies"

"We compute the equilibrium configuration of a collision-free plasma contained in an axially symmetric magnetic field. The plasma is characterized by a non-scalar pressure tensor which is obtained from a microscopic distribution function in a form suggested b the guiding center approximation. The solution is calculated in the limit where the ratio of the width to the length of the plasma region and the ratio of the gas to the magnetic pressure are both small. Boundary values at the midplane as well as the shape of the plasma appear as arbitrary parameters in the solution. We give the solution to a corresponding scalar pressure problem for comparison."

"In this paper we solve for the diffracted wave which results when a weak hydromegnetic shock impinges on a rigid perfectly conducting half plans."

None

"In our original proposal it was pointed out that we had obtained, b the successive treatment of adrenochrome with mineral acid and thiosemicarbazide, a black material which proved to be effective in preventing vascular damage cause by snake venom, radiation and thermal burns. Since the effectiveness of this preparation varied widely with different samples it was suspected that the product did not have a uniform composition. As a results of the inability of effect a separation or purification of the black product we decided to try some pure compounds related to adrenochrome. Some results obtained were reported in our proposal to renew contract AT(301\-1)-2242. Other results will be reported in the body of this report."

"A survey is presented of the theory of confinement in open-ended systems (such as mirror machines and cusped geometries) together with the slight amount of experimental confrontation with theory that exists at present."

Conclusions from the study: "Radioactive dusts are carcinogenic, and can cause cancer of the lung. complete dose response curves have not yet been determined. All the parameters that render this demonstrably toxic material (radioactive dust) have not yet been evaluated. It is strongly suggested by the experimental data that duration of radiological insult to the lung is an important factor in eliciting lung cancer. The atmospheric tolerance concentrations now in use seem to afford little margin of safety."

"Investigations into the behavior of the gas flow behind spherical or cylindrical blasts have shown that secondary shocks arise within the original detonation gases. The secondary shock, at first weak, is carried outward with the expanding gases. Subsequently it strengthens and bends back toward the origin, arriving there with high intensity. By using some recently developed techniques in shock dynamics a theory is developed by which the motion of the main shock wave, as well as the formation and subsequent motion of the secondary shock, are given by explicit formulae."

"Dust and gas masks and respirators have been an effective method under certain environmental conditions to reduce the inhalation of toxic aerosols. Under many conditions, however, their efficacy has been seriously questioned. It is the purpose of this study to evaluation over-all respirator performance on fine aerosols and to develop equipment whereby a greater degree of respiratory protection may be assured with reliability for highly toxic atmospheres."

This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).

Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-2 nuclear analysis was performed by Alco Products, in. under Tasks 1, 8, and 10 of Contract No. AT(30-2)-326 for the Atomic Energy Commission.

Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually tested. In addition, these considerations include aspects required to accurately predict the performance, operation, mechanical reliability, and feasibility of fabrication of the 70 MW design.

Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II and SM-1A Core I contain nearly identical B-10 loading of 17.79 grams, compared to the best estimate of 15.75 grams for SM-1 Core I. The available data indicates that all three cores possess similar nuclear characteristics.

This technical report represents the final design for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming fro the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to the steam generator. Because of radioactivity the unit will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shutdown it will be necessary to allow time for radioactive decay before the unit will be accessible to personnel. Because of inaccessibility and possible long periods allowed for decay time, it is imperative that the unit give trouble free operation. During periods of shutdown, the internals should have easy access for inspection and repair if necessary so that down time is held to a minimum. The steam generator is designed to generate superheated steam using liquid sodium from the intermediate heat exchanger as the heat source. Its basic design is a shell and tube unit made up of three difference sections: (1) a …

Introduction: This volume deals principally with the chemical analysis and the stress analysis for a sodium to sodium intermediate heat exchanger and a sodium to water steam generator. The work presented is an extension and modification of the analysis presented in the preliminary design report. The chemical analysis covers the sodium cover gas system and the effects of sodium-water reactions in the event of a leak in the steam generator. Considerable design work was done in an effort to maintain the integrity of the steam generator vessel under maximum leak conditions. The method of sizing relief valves for each unit under varying leak rates is presented in this text and operation of the unit for the various leak rates is resented in the Operation and Maintenance volume. The stress analysis section covers those thermal transients which would be physically possible with this intermediate heat exchanger and steam generator design. Attention has been given to methods of operation which would minimize the magnitude and frequency of thermal shocks. Certain areas have been studied in detail where thermal stresses appear high. This report also includes a structural design basis for handling stress analysis of combined mechanical, hydrostatic and thermal stresses and conditions …

Introduction: Sodium Components Material Specifications. Twenty-three material, inspection and welding specification are presented for the various parts of both the intermediate heat exchanger and steam generator. Tables indicate the applicable parts and assemblies to which these specifications shall apply. For other parts, where the material requirements are not severe, the ASTM or other indicated specifications shall apply.

This technical report contains the operation and maintenance specifications for the intermediate heat exchanger and the steam generator. The report contains eight sections: (1) General Information, (2) Shipping and Installation, (3) Operation Procedures, (4) Scram and Casualty Shutdowns, (5) Leaks, (6) Instrumentation and Control, (7) Maintenance, and (8) four Appendixes (a) Boiler Water Chemistry Recommendations, (b) Final Concept Drawings, (c) Industrial Nucleonics Literature on Liquid Level Detector, and (d) Sodium Purity Control Recommendations.

Abstract: A control system to provide digital printing and to plot an analog trace on an electric operated IBM model 11C Output Writer is described. The Digital mode of operation translates multidigit numbers through a set of commands to print each digit serially, then presents them to the output writer in a time sequence. The Analog mode of operation converts a d.c. input voltage to a digital number and by tab and space bar commands translates the carriage horizontally a distance proportional to this number.

This report undertakes research to study LiCuCl3-2H2O is from a structural standpoint, revealing the oxygen positions. The study uses the Levy-Bussing anisotropic temperature factor treatment and least squares program to determine a discrepancy factor for the visually determined intensities. The structure of the molecule is also found to have interesting magnetic properties which has inspired a new study at Brookhaven.

This report describes the method and research that led to the development of a "new type of mechanical seal for a high-voltage, vacuum pass-through...for use in a general utility 60º sector mass spectrometer." (From introductory paragraph)

This report provides a broad and in depth discussion of bismuth, discussing the properties of bismuth--including physical, electrochemical, and chemical properties. It then discusses the processes by which bismuth is detected and how bismuth can be separated and isolated, with discussions of dissolution, precipitation, and extraction.

From abstract: "The nuclide Be7 has been produced by photoactivation of Be9, B and C12 using the bremsstrahlung beam of an electron synchrotron operated at 45 Mev. Integrated cross sections for the formation of Be7 have been estimated by comparison with the Ta181([gamma],n)Ta180m reaction. The reaction C12([gamma],2p3n)Be7 has also been observed in irradiations at 30, 35 and 40 Mev maximum energy. Its yield has been compared with that of the C12([gamma],n) reaction at 45 Mev. The reaction A127([gamma],2p3n)Na22 was observed at 45 Mev."