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The Special Metallurgical Building at Mound Laboratory, a building of 18,515 sq ft of floor space, was decommissioned. This decommissioned facility formerly housed 238PU processes for the fabrication of radioisotopic fueled heat sources. The 238PU work was conducted in 585 linear ft of gloveboxes occupying approximately 12,600 sq ft of the building. All of the gloveboxes, process services, building services, interior walls, and ceilings were removed to the point of exit at the roof. Eighty-five percent of the filter banks occupying 700 sq ft of floor space was also removed. Special procedures and special equipment were used to reduce the amount of 238PU in the building from approximately 100,000 Ci at the start of the effort to less than 0.3 Ci without a significant release to the environment.

This project was initiated to study the manufacture of new explosive formulations. Production and quality parameters are determined; among these are viscosity, composition, particle size distribution, processing variables and raw materials, and their effect on operation, safety characteristics, producibility, and physical and explosive properties. Pastes, extrudables, and PBX`s are among the formulations. One 20-pound batch of XTX-8003 was made to complete a milling study and two 28-pound batches were made to fill an LRL order. No problems were encountered during the manufacturing operation, and test fire results were satisfactory. The effort to resolve some of the problems with LX-04 included evaluating reprocessing techniques and testing various binders. Outstanding elongation results were obtained with Fluorel 1700 binder. Also, a reasonably good elongation was obtained with Lot 16 Viton when the slurry coating was performed in the 100-gallon kettle. The washing and reworking, with extra solvent, of production Lot 27B improved elongation somewhat, but not enough for production acceptance.

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This document records the chart materials and talk outlines used in presentations at the Advisory Committee on Reactor Safeguards meeting of September 10, 1965, on the Irradiation Processing Department, General Electric Company, operated production reactors. The general objectives of the meeting were to review administration of safety during contractor transition, the status of N-Reactor operation and conversion project progress, and progress on the confinement studies for the production reactors. Review of the proposal to raise the K-Reactor power level limit was the specific objective of the meeting. K and N Reactor Presentation Agenda is included. The list of meeting attendees and information used for the K-Reactor tour are included in the appendix.

The information contained in this report was copied from carts used for discussions at Richland on May 4--6, 1965. Representatives of the Martin Company, US Rubber company, General Electric -- HAPO, and AEC-RL00 were present. The data represent the best current information on the quantity, quality, and availability of each fission product considered, i.e., strontium-90, cesium-137, promethium-147, and cerium-144.

The purpose of this project is to determine the thermal properties of explosives, and to continue the development and evaluation of thermal tests. Two preliminary experiments were conducted to determine (1) how the time-to-explosion (TE) using Lee Plugs (short stainless steel and aluminum) would compare with the TE obtained using the lead plugs; and (2) how the Lee Plugs would perform with du Pont`s EL-511 and Tacot at 314{degrees}C and 362{degrees}C., respectively. The Pantex-built chromatograph is operating as a two-column instrument, and the findings of an extensive check out of the instrument are reported. The chemical reactivity test sample holders were shown to evolve approximately 30{mu}l of N{sub 2} + O{sub 2} and 3 {mu}l of CO{sub 2} when heated for 22 hours. A number of thermal tests were made on two lots of LX-04-1 (39A and 38B) to determine if any differences could be detected that would explain why Lot 38B tensile strength is much better than 39A when both were made from the same lot of Viton A. Some differences were detected, but they have not been related to the tensile strength of the material. The time-to-explosion for various Adiprenes with HMX are reported, and they indicate that …

Explanation of research methods and data collected during a salmon survey at the Project Chariot site near Seattle, Washington.

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This report addresses the coupled partial differential equations for trinucleon "radial" wave functions.

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