This report contains a detailed description of a Monte Carlo analysis of a hypothetical nuclear waste repository performed for the Lawrence Livermore Laboratory as part of their mock siting exercise. Field measurements had been used to construct a hydrology model of the geologic medium surrounding a nuclear waste repository, complete with specified uncertainties. The Monte Carlo analysis has been used to ascertaln the uncertainty in the radioactive release from the repository given the uncertainty in the geohydrologic parameters, and correlation analysis has identified some input parameters that have a potentially large influence on the output (radioactivity release) uncertainty.

The research topics covered include a study of the nonlinear behavior of the drift cyclotron loss-cone instability in mirror machines and a study of the longer time behavior of the nonlinear O'Neil trapped particle saturation. The saturation amplitude for a single dominant mode near the stability onset boundary was determined for the drift cyclotron loss-cone instability for a variety of mirror-like distributions. The results are in good agreement with computer simulation studies of Cohen and Maron.

This report is a summation of three months drilling and testing activities in the four primary study areas of the WGSP: Greater Green River Basin, Northern Great Plains Province, Piceance Basin, and Uinta Basin. The core and the drilling programs are part of the resource assessment. (DLC)

The rock mechanics testing performed at the Earth Mechanics Institute of the Colorado School of Mines for Rockwell Hanford Operations under subcontract SA-917 is summarized. Cores were supplied from drill hole DC-4 on the Hanford Site, characterized geologically, and tested for thermal and physical properties for designing long-term underground storage of radioactive waste materials. The approved test procedures, results, and data analysis for this test series are presented. Uniaxial and triaxial results indicate strengths similar to drill hole DC-6, but significantly higher than drill hole DC-8. Trends with density, depth, confining pressure, and temperature, however, were similar for the three drill hole locations tested.

The experimental approach to attaining the goals of this research program is briefly outlined and the progress made in the last year is reviewed in sections entitled: (a) Primary steps in the reaction of recoiling silicon and germanium atoms and the identification of reactive intermediates; (b) Thermally induced silylene and germylene reactions; (c) Silicon free radical chemistry; (d) The role of ionic reactions in the chemistry of recoiling silicon atoms.

The use of the Oregon State University TRIGA Reactor during the year ending June 30, 1979, is summarized. Environmental and radiation protection data related to reactor operation and effluents are included.

This report details tester status and activities in support of testing of timers, actuators, detonators, firing sets, transducers, isolators, and pyrospacers for the period of April through June 1979.