The effects of seismic vibrations on the dynamic behavior of a composite system were analyzed. The equations of motion were derived and soIved with special emphasis on determining the resulting stresses. The method of analysis thus developed was applied to the composite structure consisting of the core, pressure vessel, and supporting skirt of the Experimental Gas-Cooled Reactor (EGCR). A system with three degrees of freedom was considered in order to determine the effects of an earthquake of the maximum intensity expected in the area surrounding Oak Ridge, Tennessee. The system of equations of motion was solved both numerically and analytically, and the resonant frequencies were determined. The seismic effect was shown to be small when the frequency of the seismic disturbance coincided with a natural frequency of the system. In particular, the shear stresses in the graphite core were shown to be negligible. (auth)

The objectives of the test described in this report was to determine the inventory of radionuclides in the films on standard production reactor fuel elements and the corrosion of these fuel elements as a function of position in the reactor.

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In order to provide advance direction for 333 Building equipment development work, a survey of potential areas of significant savings through equipment improvement has been made. The purpose of this report is only to indicate areas for investigation, not to define a program. Equipment is adequate to maintain operating continuity and provide for safe operation of the building. Special attention should be given to ``one-of-a-kind`` pieces of equipment. These include the press, cutoff saw, beta heat treat facility and autoradiograph film developer. Manpower savings will result principally from refinement of each operation. There are no really outstanding areas for improvement. The greatest potential for savings is in material costs. These are illustrated in Tables I&IV. Maintenance costs provide for possible significant reductions at braze, vacu-blast, nondestructive test, autoclaves, and chemical processing equipment.

This document describes the development and test of a short nozzle-mounted venturi. The development`s purpose was to permit the elimination of cavitation collapse in a reactor inlet pigtail during flush discharge.

The three alterations discussed in this report have an effect on the parameters used in Total Control Calculations for C Reactor: Conversion to smaller diameter and shorter vertical safety rods in six outer control channels; installation of forty-four overbored tubes with short fuel charges in the flat zone and an associated increase in spike enrichment; and centralization of the enrichment ring into a three-lattice unit width in place of three and one-half lattice units previously in use. New parameters are derived in this document for future total control calculations.

In the High-temperature Gas-cooled Reactor (HTGR), structural metals will be required to operate at temperatures of 1000 to 1400 deg F in an impure- helium environment for extended periods of time. Six candidate materials for such applications, including nickel alloys and stainless steels, were subjected to simulated reactor environments for times up to 3000 hr to evaluate the extent of corrosion and the changes in mechanical properties occasioned by I such exposures. Under the experimental exposure conditions (helium containing 200 to 300 ppm CO and 200 to 300 ppm H/sub 2/, or helium containing 2000 to 3000 ppm CO and 2000 to 3000 ppm H/sub 2/, at temperatures of 1200 or 1400 deg F), oxidation rather than carburization appears to be the major corrosion process; however, in some cases alternating carburization and decarburization were observed. Measurements of weight gains are described. None of the materials studied exhibited a large change in their mechanical properties after exposures at 1200 deg F. After exposures at 1400 deg F, moderate changes in mechanical properties were observed for all materials except Type 321H stainless steel, which exhibited a large decrease in ductility after l500-hr exposure to the higher impurity concentration. In general, the control …

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Maintenance of poiarization of polarized protons in a linear accelerator is known to be feasible. Circular accelerators present a different problem, and the investigation of the interaction of orbit dynamics and particle polarization in general is undertaken. The equation of motion of the spin vector of a charged particle in a magnetic field as formulated by Bargman, Michel, and Telegdi is utilized in the study of depolarization for several accelerators. High values of depoiarization are obtained, and means for avoiding such depolarization are suggested. (D.C.W.)

This report, from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

A specially designed tee, which is verified by stress analysis to be operable under the design conditions of the SCTl test installation, is shown. The main line sodium flow is changed from primary sodium flow at 1300 deg F to secondary sodium flow at 700 deg F. This is done at such a rate as to cause the downstream temperature to change 35 deg F/sec. There are 25 of these cycles. Startup causes a temperature change from ambient to 350 deg F on both lines at a rate of 100 deg F/hr. There are 5 of these cycles. The main line flow temperature is changed from 1200 to 1300 deg F in 9 seconds. There are 25 of these cycles. From the hold temperature of 350 deg F each line is raised at the rate of 100 deg F/hr. The secondary line is raised to 700 deg F and the main line to 1200 deg F. There are 300 of these cycles. At any temperature the mainline flow temperature drops 110 deg F in 7.5 minutes. There are 7000 of these cycles. Primary sodium at 1300 deg F mixes with secondary sodium at 1100 deg F to give a main …

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At 10:59 AM (PST), Saturday, April 7, 1962 a criticality accident occurred in a plutonium waste chemical recovery facility at the Hanford Atomic Products Operation, operated for the Atomic Energy Commission by the General Electric Company. Four men were hospitalized but were released after medical observation and after estimates of the radiation doses received were available. This report describes the dosimetry investigation that was made following the accident. This investigation was facilitated by the fact that all employees affected had personnel dosimeters in their possession when the incident occurred. The interpretation of the data supplied by these dosimeters was supplemented by information gathered by techniques that were developed in connection with other accidents. Below, the available information is first presented and then applied in a discussion of the dosimetry of the people involved in the accident.