Thermal analysis of the LOFT containment vessel penetration S-6A was conducted for steady-state operation and blowdown transients. Penetration S-6A is a 20-inch pipe through which passes a 10-inch pipe from the steam generator containing 600/sup 0/F steam. Recommendations for penetration S-5E were based on the analysis of penetration S-6A. Penetration S-5E is an 18-inch pipe through which pass a 4-inch pipe containing the steam generator feedwater at 430/sup 0/F and a 0.5-inch pipe containing sample water at 600/sup 0/F. The thermal analysis is necessary to determine the maximum temperature gradient in the containment vessel around the penetrations. The outside of the penetrations protrude into a room adjacent to the containment vessel which will be maintained at a minimum temperature of 50/sup 0/F. The steady-state temperature inside the containment vessel was assumed to be 100/sup 0/F. Table I of LOFT Containment Vessel Specification S-1 was used for inside transient temperatures.

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.

A summary of measured data collected by numerous agencies cooperating in the Piledriver event, is presented together with calculations based on empirical relations deduced from past events in comparable media. Of 9 relations that have been proposed to predict cavity radius, 5 result in radii accurate to <3.5%. The remainder are off by about 10 to 18%. Three postshot recovered cores (U-15.01 PS-1, -2, -3) were examined on a gross scale prior to extensive detailed sampling for laboratory tests. The positions of injected glass seams, radioactivity, and shear zones were recorded. The orientation of several thousand core fractures was measured with respect to the core axes and distance from the shot point. Taking all observations into account, phenomena related to failure of rock is the Piledriver event are closely related to pre-existing weaknesses and inhomogeneities. (Longer abstract available)

The scope of this research program is to study the structure of nuclei and the properties of the nuclear force, in particular its symmetries, using the tools of nuclear spectroscopy. To this end a unique set of instruments is at disposal, including curve crystal diffraction monochromators, high resolution beta spectrometers and Moessbauer spectrometers.

This report discusses the causes and effects of dust storms in the Tri-Cities area.

This report details activities of Pacific Northwest Laboratory`s Division of Production and Hanford Plant Assistance Programs for the month of March 1970.

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The intent of this report is to record, in one place, the significant historical events associated with the Single Pass Reactors from initial startup through December 1969. Significant events are chronologically listed in Section 1 and specific programs are summarized in Section 2.

This report provides reactor output production information for calendar year 1969.

The purpose of this study is to review the current status of gaseous and liquid effluents that have a potential for release of radioactivity to the environs from ARHCO operations in the 200 Areas. Non-radioactive pollutants to the environs are not included in this study. The study provides a complete compilation of the active effluent streams released to the environs including associated monitoring and sampling equipment and analytical procedures. Recommendations are made for improved monitoring and sampling of the active effluent systems which, in the opinion of the Personnel Protection Section, are now inadequate.

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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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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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This report presents a trade study of design concepts for the Control Drum Actuator System, a component of the NERVA Nuclear Subsystem (NSS). The purpose of this study is to evaluate and select the most logical and reasonable approach for continued detailed design and development of this component, consistent with the programmatic and technical requirements for the ten-hour full-flow cycle engine as defined in the NERVA Program Requirements Document.

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