7 Matching Results

Search Results

Advanced search parameters have been applied.
in creator/contributor: "Munnecke, V. H."  
Results: 1 - 7
open access

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT

Description: Work reported includes: Chemical-Metallurgical Processing; Fuel Cycle Applications of Volatility and Fluidization Techniques; Calorimetry; Reactor Safety; Energy Conversion; and Determination of Nuclear Constants.
Date: July 1, 1963
Creator: Lawroski, S.; Vogel, R. C.; Levenson, Milton & Munnecke, V. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Engineering Division Summary Report

Description: Measurement of radioactive carry-over was made on borax III operating at 300 psig and at power levels ranging from 4 to 14 mv. Decontamination factors of from 1.5 x 104 (at 14 mv) were obtained. These data are in essential agreement with those predicted by previous laboratory experimental work.
Date: May 2, 1956
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Engineering Division Summary Report July, August, and September, 1956

Description: Additional runs have been made in the six-inch, continuous-flow mixing chamber to study the rate of mass transfer between isobutanol and water. These runs were inconclusive because the effluents were mutually saturated. A new four-inch cell has been designed and is being fabricated; this will permit a reduction in the time available for mass transfer. Consideration has been given to other liquid pairs which may transfer more slowly than isobutanol-water. The system nitrobenzene-ethylene glycol … more
Date: December 1956
Creator: Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Engineering Division Summary Report October, November, and December, 1956

Description: A final series of runs was made in a four-inch continuous-flow mixing chamber to study the transfer of isobutanol into water and nitrobenzene into ethylene glycol. Satisfactory techniques were developed to provide for the rapid analysis of these systems. In addition, a light-scattering correlation was prepared to provide a measure of the interfacial area of the yellow-colored nitrobenzene-ethylene glycol mixtures.
Date: March 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Engineering Division Summary Report July, August, and September, 1957

Description: Development work continued on a fused salt process for the recovery of uranium from zirconium-matrix fuel alloys. The fuel is dissolved in a sodium fluoride-zirconium fluoride melt at 600°C by hydrogen fluoride sparging. The melt is then sparged with fluorine gas which volatilizes the dissolved uranium as the hexafluoride. The final decontamination and purification of the uranium hexafluoride are accomplished by fractional distillation. The testing of graphite as a container material for the hy… more
Date: December 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Engineering Division Summary Report for January, February, and March 1957

Description: A fused fluoride process for dissolution of zirconium-uranium fuel alloys is being developed. The alloy is dissolved in an equimolar sodium fluoride-zirconium fluoride melt at 600°C by sparging the system with hydrogen fluoride. The uranium is volatilized from the melt as the hexafluoride by a sparging operation with fluorine or bromine pentafluoride vapor. This product is then decontaminated and purified by fractional distillation.
Date: July 1957
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Engineering Division Summary Report for January, February, and March 1958

Description: Development work was continued on the fused fluoride process for the recovery of enriched uranium from zirconium-matrix fuel alloys. The alloy is dissolved by immersing it in molten sodium fluoride-zirconium fluoride at 600°C and passing hydrogen fluoride vapor through the system.The dissolved uranium tetrafluoride in the melt is then volatilized as uranium hexafluoride by sparging with fluorine. The uranium hexafluoride product is purified and decontaminated by fractional distillation. Additio… more
Date: June 1958
Creator: Lawroski, Stephen; Rodger, W. A.; Vogel, R. C. & Munnecke, V. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen