Gas residence time distributions were determined for a stirred tank carbonation reactor. Empirical correlations for the first and second moments of the residence time distribution (RTD) curves as functions of flow rates and impeller speeds were obtained. Decontamination factors for /sup 85/Kr were measured.

Development of the calorimeter equilibrium prediction program has been completed, and tests of the software program have been conducted on calorimeters ranging from 1 to 6 in. (2.5 to 15 cm) in diameter and power inputs between 0.1 and 8.3 W. Equilibrium values have been predicted with relative accuracies of better than 0.1% (95% confidence) and with an average time improvement factor of 2.1, which represents a 52% time saving, for every test case. A computer code is being developed by the University of Cincinnati to describe the steady-state heat transfer in a resistance bridge calorimeter. The computer program which is based on the theory of heat transfer analysis by finite differences has been written and is being checked against experimental data. Following the development of the steady-state code, work will commence on the transient heat flow analysis. The effect of R. Gunnink's new plutonium branching ratios on previous plutonium isotopic ratio measurements is demonstrated. For measurements relative to plutonium-239 the biases change from between 2 and 7% low to between 2 and 13% high. For measurements relative to plutonium-241 the changes in bias are within the statistical uncertainties normally reported for these peaks. In preparation for the proposed demonstration …

Extraction, or reverse-phase partition chromatography, as used mostly for analytical separations, employs an organic solvent extractant as a stationary phase on an inert support material. This technique, which has the advantage of utilizing the versatility of solvent extraction systems with the less expensive operation of ion exchange equipment, was evaluated for a process to recover low level concentrations of americium from acidic process waste streams at Rocky Flats. The bidentate organophosphorous extractant DHDECMP (dihexyl-N, N-diethylcarbamylmethylene phosphonate) was used as the stationary phase since it was shown to effectively scavenge americium from acidic waste streams without significantly extracting impurity ions. Over 30 support materials were evaluated for DHDECMP capacity and for their ability to retain the extractant. Of the supports tested, the Amberlite XAD macroreticular sorbents were found to have the highest DHDECMP capacity. Amberlite XAD-4 beads retained the extractant significantly better than the other supports evaluated. Thus, this solvent was tested for americium breakthrough capacity and compared to the theoretical capacity.

The list of outstanding debts for the League of United Latin American Citizens: includes settled accounts, those not claimed, and attorney's fees paid by League of United Latin American Citizens.

The bounce-average computer code simulates the two-dimensional velocity transport of ions in a mirror machine. The code evaluates and bounce-averages the collision operator and sources along the field line. A self-consistent equilibrium magnetic field is also computed using the long-thin approximation. Optionally included are terms that maintain ..mu.., J invariance as the magnetic field changes in time. The assumptions and analysis that form the foundation of the bounce-average code are described. When references can be cited, the required results are merely stated and explained briefly. A listing of the code is appended.

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication.

This report addresses Disposal of Dredge and Fill regarding Water Pollution Control.

This selected bibliography concerning the U.S. Senate is based off of works that were contemporary at the time of writing as well as older, major works.

It is the unanimous conclusion of the Ad Hoc Committee that radioactive waste can be stored in salt and underground repository sites sufficiently removed from natural and/or man-made dissolution areas so that the waste will not be liberated during its hazardous period at projected rates of future salt dissolution. To ensure long-term isolation of radioactive waste in salt formations, specific recommendations are given for needed research concerning (A) General Principles, (B) Basinal or Regional Studies, and (C) Site-Specific Studies, each stated in sequence of priority.