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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
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Corrosion of Plutonium Alloys in NaK

Description: A plutonium-aluminum alloy containing 4 atom per cent aluminum showed no attack after exposure to purified NaK for one month at 400 C in the absence of any oxide. The same specimen and other plutonium alloys, including pure plutonium, showed marked deterioration in shorter exposure in the presence of oxide films from a welded stainless steel container. Pure uranium was resistant even in the presence of such oxides.
Date: July 1953
Creator: Hyman, H. H. & Katz, Joseph J. (Joseph Jacob), 1912-2008
Item Type: Refine your search to only Report
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Dissolution of Uranium Oxide Arising From Slug Failure

Description: The purpose of this work was to study reagents which might be effective in dissolving uranium oxide produced during slug failures in water-cooled reactor systems. An aspect of this problem which has subsequently become of primary importance is the solubility or transportability of the oxide in pure water.
Date: July 1953
Creator: Johnston, F. J.; Wills, P. E. & Katz, Joseph J. (Joseph Jacob), 1912-2008
Item Type: Refine your search to only Report
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Reactor Engineering Division Quarterly Report Section I January, February, March. 1956

Description: Physical calculations have been performed for various combinations of the four types of fuel assemblies to be used in the EBWR core. Two thicknesses of plates (0.205 in. and 0.274 in., including two 0.020-in. cladding layers) are to be made of both natural uranium and uranium containing 1.44% U235. Any given fuel assembly contains six identical plates. A total of 148 assemblies, 74 natural and 74 enriched, are to be fabricated. Various configurations of these fuel assemblies can be used to (1) … more
Date: July 1956
Creator: Members of the Reactor Engineering Division
Item Type: Refine your search to only Report
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Testing of Fuel Element Parts and Assemblies by the Radiographic Method

Description: Concurrently with the production of canned uranium slugs for pile operation there arises the problem of nondestructive testing so that no slug which may fail structurally during operation be placed in the pile. The ultimate goal of any such testing program is to devise nondestructive testing methods which will eliminate defective slugs. A secondary goal of the testing program is to learn as much as possible about the construction of the canned slug so that the mechanisms of failure can be under… more
Date: July 1, 1954
Creator: VanderLaan, Robert H.
Item Type: Refine your search to only Report
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The Use of the Electrical Conductivity of Graphite as a Radiation Damage and Flux Monitor. Implications of the Results to the General Theory of Radiation Damage

Description: A method for monitoring radiation damage irradiations using the change of the electrical conductivity of graphite is described. Results of monitoring operations in a number of locations are given. An attempt is made to explain the damage rate found in the converter at CP-3. An estimate of the flux spectrum in VT-4 and the converter of CP-3 is made and the damage rate is computed according to theories of Seitz and James. It is found that the experimental results are more in accord with the predi… more
Date: July 13, 1953
Creator: Primak, W. L. & Fuchs, L. H.
Item Type: Refine your search to only Report
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