This report describes the basic design, intermediate and final stacking procedures, and graphite behavior of nuclear reactors DR and H during construction. Included in the report are test records to substantiate basic design assumptions and data and the actual performance of the graphite during preliminary and final stacking.

By use of the assumption that the pressure-volume relation is linear, a solution to the problem of designing a cascade for a given turning and with a prescribed velocity distribution along the blade in a potential flow of a compressible perfect fluid was obtained by a method of correspondence between potential flows of compressible and incompressible fluids. The designing of an isolated airfoil with a prescribed velocity distribution along the airfoil is considered as a special case of cascade. If the prescribed velocity distribution is not theoretically attainable, the method provides a means of modifying the distribution so as to obtain a physically significant blade shape. Numerical examples are included.

Labcratory data which indicate that the recovery of Pu and U and decontamination from fission products are feasible in a solvent extraction process using tributyl phosphate are given. The procedure consists of extracting Pu(IV) and U with 15% TBP--85% Varsol using 5.0 N HNO/sub 3/ as a salting agent. (J.R.D.)