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This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of November 1968.

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Electrons were injected from a 3.3-MeV 300-A accelerator into a circular orbit in a pulsed magnetic field. Trapped ring currents of 150 A (4 x 10{sup 12} electrons) were magnetically compressed from 19 cm to 3.5 cm radii and simultaneously accelerated from 3.3 MeV to 18 MeV in energy. The rms dimensions of the cross section of the ring after compression were a = 2.3 {+-} 0.2 mm radially and b = 1.6 {+-} 0.2 mm axially. The lifetime of the ring was typically 5.5 msec, and was determined by the decay of the magnetic field after compression. This lifetime could be decreased by the addition of hydrogen gas, indicating the focusing effect of the trapped positive ions.

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The purpose of this Conceptual Facility Design Description (CFDD) is to provide a technical description of the Inert Gas Cell Examination Facility such that agreement with RDT on a Conceptual Design can be reached . The CFDD also serves to establish a common understanding of the facility concept among all responsible FFTF Project parties including the Architect Engineer and Reactor Designer. Included are functions and design requirements, a physical description of the facility, safety considerations, principles of operation, and maintenance principles.

This report is a summary of several studies made by the author during 1967, and early 1968, while providing technical assistance to the Advanced Concepts and Planning Section. An attempt has been made to reduce the data to a usable form which will enable the reader to estimate the production of a particular isotope and the production of weapons grade plutonium that accompanies the co-product loading for different Uranium-235 concentrations of the driver fuels. It should be emphasized that the production data shown in this document do not constitute an engineering study of the loading. As the safety analysis has not been performed and only minimal hydrokinetics have been studied, it is imperative that the use of the data contained in this report be used only for planning and estimating work. if any particular loading were to become a reality, a detailed engineering study would be required for that loading. Although the B Reactor has been deactivated it is included in the report along with the C and K Reactors. Hence, it is possible to make estimates of the capabilities of the entire Hanford single pass reactor complex. Although Oralloy fuel for the Hanford reactors for isotope production has not …

The magnitude of the deviations from roundness of molded detonator heads, caused by the geometry of the part and by different materials, was investigated to provide a scientific basis which can be used to predict dimensions and tolerances of size and roundness for new heads. Injection presses were used to mold detonator heads to precision tolerances. Twenty parts were molded under optimum conditions in two different molds using both DAP filled with long glass fibers and DAP filled with asbestos. Each of the parts was analyzed for size and roundness, and the data were analyzed statistically. The results indicate: 1. Geometry is highly significant. 2. Material is highly significant. 3. Geometry and material do not interact. 4. Geometry affects magnitude of deviation from roundness. 5. Geometry affects magnitude of shrinkage.

This report gives the status of production tests control tube loadings in reactor process tubes containing significant amounts of SS material. All data are given in table form. For further description of column headings and the current discharge goal exposure plan refer to Document DUN 3443.

Douglas United Nuclear, Inc., operates for the AEC at the Hanford reservation four production reactors and their fuel preparation facilities. The production reactor plants are located on the south bank of the Columbia River approximately 30 miles northwest of Richland. The fuel preparation plants, located about 5 miles north of Richland are also on the Columbia River. This report provides identification of such facility; a brief description of functions and environs; and schematic diagrams of processes which generate radioactive wastes. A discussion of process characteristics which determine quantity and quality of wastes is provided.

This document provides data collected by the Controlled Temperature Tensile Capsule (TISR-243).

The FFTF Radioactive Waste System provides the equipment and facilities required for the routine collection, transfer, storage, and disposal of radioactive liquid and solid wastes. Radioactive solid wastes and radioactive liquid wastes not normally piped t o the Radioactive Waste System Receiving tanks, are packaged inappropriate containers by the systems generating the waste for collection and disposal by the Radioactive Waste System. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.