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Chemical Engineering Division Summary Report
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.
System:
The UNT Digital Library
The Fabrication of Prototype Fuel Elements for the Experimental Boiling Water Reactor and the Experimental Breeder Reactor
The purpose of this program was to develop techniques and methods for producing fuel elements for the Experimental Boiling Water and Experimental Breeder Reactors. Methods for fabricating large tubes, flat plates, and small pins were investigated. The tube and plates contained U-5 w/o Zr-1.5 w/o Nb alloy and were designed for the EBWR. The pins contained U-2 w/o Zr alloy and were designed for the EBR. Cladding and end seal material of Zircaloy-2 was required for the water-cooled EBWR elements. Unalloyed zirconium was specified for cladding on the sodium-cooled EBR elements.
Date:
May 1956
Creator:
Sawyer, H. F.; Paynton, W. C.; Loewenstein, P. & Corzine, P.
System:
The UNT Digital Library
Growth Rates and Microstructural Characteristics of 300 C Rolled Uranium Rods on Thermal Cycling
The thermal cycling growth and the accompanying metallographic changes were studied in 300 [degree] C rolled uranium rods up to 3000 cycles. The growth rate was found to decrease at the higher cycling levels. Project-grade material developed substantial porosity during cycling; high purity material showed no evidence of porosity.
Date:
May 1956
Creator:
Chiswik, H. H. & Mayfield, R. M.
System:
The UNT Digital Library