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Machining & installation of graphite for 105 DR & H
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.
Date:
October 1, 1949
Creator:
MoKenna, W. R.
System:
The UNT Digital Library
PUREX PROCESS FOR PLUTONIUM AND URANIUM RECOVERY
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.)
Date:
October 1, 1949
Creator:
Lanham, W. B. & Runion, T. C.
System:
The UNT Digital Library