This is the first of two papers in which the low-temperature properties of liquid He{sup 3} are to be calculated in the thermodynamically consistent 'T-matrix' approximation. The set of coupled integral equations which are to be solved is exhibited in Part A of this paper. Part B of this paper is devoted to a preliminary, zero-temperature calculation which employs the additional approximations of using separable potentials and a noninteracting spectral function to define the interaction of two particles in the medium: the <T>{sub 0} approximation. In this approximation they obtain a spectral function for the quasi particles which they expect to display general features in common with those of the actual spectral function. Using this spectral function, they calculate the thermodynamic properties of the system and find that they compare favorably to those obtained in other calculations.

Confinement studies on the Hanford Production reactors were started in March at the request of the Richland Operations Office. The confinement studies were then undertaken with the following objectives established: (1) review and reestablish if necessary, the maximum credible accident for the production reactors operated by Douglas United Nuclear (DUN); (2) evaluate the present confinement systems under the Code of Federal Regulation Title 10, Part 100, Reactor Site Criteria, for the maximum credible accident and an accident corresponding to the failure of reactor fuel containing 50% of the reactor`s fission product inventory; (3) establish improvements or additions in the confinement system needed to more nearly comply with 10 CFR Part 100 radiation dose criteria for existing boundaries of the exclusion area and the low population zone for the maximum credible accident; and (4) list facility additions and changes required to comply with 10 CFR Part 100 criteria for more serious accidents than the maximum credible accident. This report presents the interim status of the confinement studies in meeting the listed objectives and lists the improvements which might be used to bring the reactors nearer to compliance with 10 CFR Part 100.

The Purex Processing Measurements Quality Control Program was designed to provide for orderly accumulation of measurements data suitable for statistical evaluation and to identify those elements of a measurement which, if improved, would result in significant reduction in overall measurement variation. This report gives an analysis of the audit data obtained at four transfer stations: L9 plutonium product loadout, K6 uranium product to storage, F15 salt waste to F16 and D5 dissolved feed to process. Estimates of variation caused by analytical, sampling and volume or weight instrumentation were computed and combined to give variation associated with a single batch transfer. Procedures for collection of future data that are more suitable for statistical evaluation are suggested. Methods used to compute random and fixed variation estimates are discussed.

The purpose of this report is to summarize and document the significant historical events pertinent to the operation of the Chemical Processing facilities at Hanford. The report covers, in chronological order, the major construction activities and historical events from 1944 to September, 1965. Also included are the production records achieved and a history of the department`s unit cost performance.

This monthly research and development report details activities of the Irradiation Processing Department for the month of October 1965.

This monthly report details the Research and Engineering Section Irradiation Processing Department`s activities for the month of October 1965.

This report discusses an allocation of $1,320,000 of 02 Reactor and Metallurgy funds which was previously made to the Pacific Northwest Laboratories. The Process Technology work order support which N-Reactor Department expected to provide during FY 1966 was estimated. The R&D allocation was based on the 189 budget proposals which were prepared early in 1965 and program identifications were provided. The integrated five year research and development program was subsequently formulated with the assistance of Pacific Northwest Laboratories and research and development program missions were defined. Revised 189 proposals have been prepared and the work is being reprogrammed in accord with the mission plan. These program discussions outline research and development needs and BNW allocations in accord with the mission requirements. The level of R&D is maintained at the original level specified in reference 1 ($1,320,000), with the exception that $130,000 for the payment of offsite irradiation unit costs is now held within NRD.

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The velocity of thermal repulsion of large aerosol particles has been calculated by others by equating the thermal force on a stationary partlcle to the Stokes-Cunningham viscous force. This procedure is theoretically unsound because the boundary conditions employed in the viscous force equation are erroneous when the particle moves in a thermal gradient. In the current study these difficulties have been circumvented by rederiving the thermal force equation, allowing for a relative velocity between the particle and the gas stream. The velocity of motion is then calculated by setting the net force on the particle equal to zero. The velocity obtained by this more realistic approach agrees with that calculated by the former method, which is surprising in view of the incorrect boundary conditions employed in the former method. Investigation of the drag force equation shows that the thermal force and the viscous force are exerted independently of each other, which explains this unexpected agreement, The range of applicability of the analysis is explored by comparison with available experimental data,

A cost analysis has been made for non-radioactive demonstration tests for the process dissolution of lithium-aluminate (or similar) ceramic in sodium tetraborate molten glass. The tests described in this report demonstrate the more important aspects of tritium production by molten glass dissolution of a high melting temperature lithium-bearing irradiated ceramic.

This report provides a review of the KE Downcomer development test, model data from the K-Downcomer tests, and a discussion of cavitation and bubble formation in nearly saturated water flow.

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