This report summarizes releases of radioactive waste to the environs of the Savannah River Plant during the calendar year 1969. Total quantities of radioactive waste released from plant startup through 1969 are also reported. Accuracy is not always implied to the degree indicated by the number of significant figures reported. Values were not rounded off, since data will be used in future cumulative summaries. No explanations are given for unusual releases; this information may be found in the Radiological Sciences Division Monthly Reports and in the Semi-annual and Annual Environmental Monitoring Reports for 1969.

This document contains information about the activities of Douglas United Nuclear at the Hanford site during the month of March 1970.

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Abstract: A system of COBOL (COmmon Business Oriented Language) computer programs which index bibliographic information recorded in KWIC INDEX format is described. A description of the system, instructions on how to use it, and examples of uses are presented. Appendicies contain a system flow chart, input data format, program descriptions, job control language and program source listings.

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Quarterly report regarding the activities of the Yankee Core Evaluation Program, the purpose of which is to evaluate the performance of the core used in the Yankee Plant and to compare actual performance with predictions, as well as the revision of designs to address any differences between actual and predicted performance.

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The design and analysis for the the coupling, gear, locking mechanism, actuator rotor-shaft and actuator bearings have been completed. Drawings reflecting the current configuration of these components have been released and are listed below. The listed assemblies are being fabricated.

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Relationships necessary for ring stability are derived between the self-focusing forces of an electron ring and the magnetic field gradient defocusing forces present near and just subsequent to the start of ring acceleration.

A calculation is given of the radiated energy loss from a charged rod which moves at constant speed past an infinite set of parallel semi-infinite conducting plates of infinitesimal thickness, with the rod taken parallel to and at a fixed distance from the plate edges. The problem is analyzed using the Wiener-Hopf technique, and the resulting formulas are evaluated analytically in the limits of high rod speed and low rod speed, and compared with numerical evaluation over the full range of speeds.

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Data are presented on the radioactivity in environmental samples collected within the Hanford plant boundaries during the first six months of 1969. Data are included on the total BETA activity and content of /sup 90/Sr and tritium in samples of Columbia River water; the total BETA activity in samples of drinking water; the total alpha and BETA activity and content of /sup 137/ Cs, /sup 51/Cr, and /sup 65/Zn in samples of su rface waters; the content of /sup 32/P, /sup 40/K, /sup 134/Cs, /sup 137/Cs, and /sup 65/Zn in the tissues of game birds feeding on the area; the total BETA activity and content of /sup 131/I in samples of surface air; the total alpha , total BETA , and total gamma activity and content of /sup 95/Zr-Nb, /sup 106/Ru, /sup 131/I, /sup 137/Cs, /su p 140/Ba, and /sup 144/Ce in samples of air filters; the total alpha and total BETA activity and content of /sup 137/Cs and /sup 144/Ce in samples of vegetation; and results of aerial surveys of gamma activity conducted at an altitude of 500 feet. Estimates were made of the average external gamma exposure rates of personnel. Increased BETA activity in the atmosphere was due …

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This document is one of a series of Departmental Reports which will document NERVA design and performance requirements at engine, sub-system, and component levels. These reports are intended to provide a single source for maintenance and documentation of design criteria and functional performance requirements, and may be used to display a continual assessment of overall design maturity.

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A hexagonal shield module of BATH material is thermally shocked at -27°F/second on its periphery by flowing chilled helium (-320°F) through the module 1D at a mass flow rate of 1.1 pounds/second. A ramp rate of -24°F/second is the calculated shield module temperature ramp associated with propellant flow and temperature requirements to simulate a mid-map startup nozzle chamber temperature ramp of 150°F/second. The resultant strains are converted to stresses and compared with calculated stresses. The maximum calculated tensile stress is 6300 psi and the corresponding minimum ultimate strength is 15,200 psi. The post-test calculated stresses and the test results are in reasonable agreement.

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