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Analysis of a standard Pu solution by the control laboratories in 231 and 234-5 Buildings
A solution of Pu was prepared for use in a re-investigation of the present 49 titration method. Three 500 microliter portions of the sample were dried and ignited to PuO{sub 2}. From the weight of the residue and the impurity analysis, the concentration, in g/l, of the solution was found to be 222.2, 221.5, and 222.5; average of 222.0. The six samples submitted to the control laboratory in Bldg. 231 were reported as: 219.3, 223.6, 221.5, 220.9, 222.3, and 228.2 (re-run 229.3); average of 222.6 g/l. The 234-5 Laboratory reported: 228.2, 233.3, 220.2, 236.1, 225.2 (re-run 220.6), and 227.9; average of 227.3 g/l. Since the standardization was carried out on April 13, the 231 Lab received its samples on May 11, and the 234-5 Lab received their samples on May 23, a correction for increase in concentration due to decomposition of the water by alpha particles and evaporation was calculated. It was determined that the results reported by the 231 Lab were very consistent (except for one determination) and that the average value agreed with the gravimetric determination. The average results from the 234-5 Lab are 2% higher than the gravimetric results. Further studies are being made on the chemical …
Date:
July 14, 1950
Creator:
Barton, G.B.
System:
The UNT Digital Library
COMPARATIVE BEHAVIOR OF A 1.8 ATOM % CHROMIUM-URANIUM ALLOY AND NORMAL URANIUM ON THERMAL CYCLING
None
Date:
July 14, 1950
Creator:
White, D.W.
System:
The UNT Digital Library
Limits of pile operating level
This report, compiled by Mr. W. R. Lewis of the Pile Technology Division, is a revision of Document HW-15516 (January 5, 1950) in consideration of new knowledge obtained during the past year. The document discusses the technical factors involved in attaining higher power levels in the various Hanford Piles. The purpose of this presentation is to summarize the present operating limitations and the possibilities of increased production rates. The limitations discussed are: A. Reactivity and flattening; B. Aluminum thimbles; C. Graphite temperature considerations; D. Boiling or vapor binding considerations; E. Tube and slug jacket corrosion; F. Effluent water activity; G. Distortion of the biological shields; H. Radiation considerations; and I. Pile control system capacity.
Date:
December 14, 1950
Creator:
Woods, W. K. & Lee, E. P.
System:
The UNT Digital Library
LITERATURE SEARCH ON LEAD-BISMUTH ALLOYS
BS>The use of a lead-bismuth alloy as a coolant in the removal of heat from power-generating nuclear reactors was considered with the possibility that its ternary alloy with uranium or plutonium might be of use in a reactor of the circulating-liquid-fuel type. Information collected from the literature covering phase-equilibrium studies, physicalproperty data, and reactivity of this alloy toward other substances is presented. (auth)
Date:
February 14, 1950
Creator:
Lee, M.E.
System:
The UNT Digital Library
Monthly Health Information Report. March 1-31, 1950
None
Date:
April 14, 1950
Creator:
Boozer, A. H.
System:
The UNT Digital Library
SEPARATION OF ZIRCONIUM AND HAFNIUM. PROPOSAL FOR CONSTRUCTION AND OPERATION OF ZIRCONIUM PRODUCTION PLANT
None
Date:
March 14, 1950
Creator:
Googin, J.M. & Strasser, G.A.
System:
The UNT Digital Library
Studies in the Carbonate-Uranium System Part I. Investigations in the Four Component System UO$sub 3$-Na$sub 2$O-CO$sub 2$-H$sub 2$O
None
Date:
December 14, 1950
Creator:
Blake, C. A.; Lowrie, R. S.; Hill, D. G. & Brown, K. B.
System:
The UNT Digital Library
Urine Assay Procedure at the Mount Laboratory. Final Report
None
Date:
April 14, 1950
Creator:
Spoerl, E. S.
System:
The UNT Digital Library