This report presents the work performed during the period May 1, 1952 to June 30, 1952. Investigation of the sodium-amalgam reduction of carbonate leach solution was continued. Additional tests on the reaction characteristics of the process are presented which extend and confirm the work reported in RMO-2605. Tests were continued to obtain information on the operational characteristics of various types and modifications of column contractors in order to evolve a design best suited for use in a continuous production operation. Work was started on a program for the further investigation of electrolytic reduction of carbonate leach solutions. A diaphragm cell which was designed and constructed for the initial tests is described. The results ar...
A process for the removal (and recovery) of vanadium from carbonate leach solution has been develope...
7 9 7 D 8 8 9 9 7 7 ; 8 < fuel-reprocessing plant using pyrometallurgical procedures is being design...
Treatment of Hot Liquid Waste: Three runs, D-73, D-74, and D-75, were made in the model clarifloccul...
This report presents the work performed during the period July 1, 1952 to August 29, 1952. Test data...
This report covers first results of work undertaken for the purpose of developing a method, suitable...
An economic analysis is presented of the sodium-amalgam reduction process for the recovery of uraniu...
This topical report describes progress made in chemical dissolution and recovery of uranium from pho...
The Idaho Chemical Processing Plant did not operate on fuel recovery during this period, due to exte...
A concentration cell electrode was installed in a fritted glass surface and was used to measure the ...
Chemical-Metallurgical Processing. A direct-cycle pyrometallurgical fuel-processing plant is being c...
Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to con...
The feasibility was demonstrated of the use of liquidorganic scintillators in contact with an alpha ...
"Data are given for leaching ores from Lukachukai District, Arizona with sulfuric acid or sodium car...
Two alternate systems, acetic acid-nickel and acetic acid-cobalt, were examined for possible replace...
In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, corrosion testing...
A process for the removal (and recovery) of vanadium from carbonate leach solution has been develope...
7 9 7 D 8 8 9 9 7 7 ; 8 < fuel-reprocessing plant using pyrometallurgical procedures is being design...
Treatment of Hot Liquid Waste: Three runs, D-73, D-74, and D-75, were made in the model clarifloccul...
This report presents the work performed during the period July 1, 1952 to August 29, 1952. Test data...
This report covers first results of work undertaken for the purpose of developing a method, suitable...
An economic analysis is presented of the sodium-amalgam reduction process for the recovery of uraniu...
This topical report describes progress made in chemical dissolution and recovery of uranium from pho...
The Idaho Chemical Processing Plant did not operate on fuel recovery during this period, due to exte...
A concentration cell electrode was installed in a fritted glass surface and was used to measure the ...
Chemical-Metallurgical Processing. A direct-cycle pyrometallurgical fuel-processing plant is being c...
Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to con...
The feasibility was demonstrated of the use of liquidorganic scintillators in contact with an alpha ...
"Data are given for leaching ores from Lukachukai District, Arizona with sulfuric acid or sodium car...
Two alternate systems, acetic acid-nickel and acetic acid-cobalt, were examined for possible replace...
In the program on pyrochemical and dry processing methods (PDPM) for nuclear fuel, corrosion testing...
A process for the removal (and recovery) of vanadium from carbonate leach solution has been develope...
7 9 7 D 8 8 9 9 7 7 ; 8 < fuel-reprocessing plant using pyrometallurgical procedures is being design...
Treatment of Hot Liquid Waste: Three runs, D-73, D-74, and D-75, were made in the model clarifloccul...