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in subjects: "Highly Enriched Uranium"  
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Use of tracers in materials-holdup study

Description: Holdup measurements of special nuclear materials in large processing facilities offer considerable challenges to conventional nondestructive-assay techniques. The use of judiciously chosen radioactive tracers offer a unique method of overcoming this difficulty. Three examples involving the use of /sup 46/Sc and fission products from activated uranium in large-scale experimental studies of uranium holdup are discussed. A justification for the method and its advantages along with examples of succ… more
Date: January 1, 1983
Creator: Pillay, K.K.S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Operation of automated NDA instruments for in-line HEU accounting at Y-12

Description: Two automated nondestructive assay instruments developed at Los Alamos in support of nuclear materials accounting needs are currently operating in-line at the Y-12 Plant for recovery of highly enriched uranium. One instrument provides the HEU inventory in the secondary solvent extraction system, and the other monitors HEU concentration in the secondary intermediate evaporator. Both instruments were installed in December 1982. Operational evaluation of these instruments has been a joint effort o… more
Date: January 1, 1983
Creator: Russo, P. A.; Strittmatter, R. B.; Sandford, E. L.; Jeter, I. W.; McCullough, E. & Bowers, G. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Nuclear criticality assessment of LEU and HEU element storage

Description: Criticality aspects of storing LEU (20%) and HEU (93%) fuel elements have been evaluated as a function of /sup 235/U loading, element geometry, and fuel type. Silicide, oxide, and aluminide fuel types have been evaluated ranging in /sup 235/U loading from 180 to 620 g per element and from 16 to 23 plates per element. Storage geometry considerations have been evaluated for fuel element separations ranging from closely packed formations to spacings of several centimeters between elements. Data ar… more
Date: January 1, 1983
Creator: Pond, R.B. & Matos, J.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Comparison of safety parameters and transient behavior of a generic 10 MW reactor with HEU and LEU fuels

Description: Key safety parameters are compared for equilibrium cores of the IAEA generic 10 MW reactor with HEU and LEU fuels. These parameters include kinetics parameters, reactivity feedback coefficients, control rod worths, power peaking factors, and shutdown margins. Reactivity insertion and loss-of-flow transients are compared. Results indicate that HEU and LEU cores will behave in a very similar manner.
Date: January 1, 1983
Creator: Matos, J.E.; Freese, K.E. & Woodruff, W.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Impact of the propylene glycol-water-borax coolant on material recovery operations

Description: The reaction of the propylene glycol-water-borax coolant with nitric acid has now been studied in some detail. This document is intended to provide a summary of the results. Findings are summarized under nine headings. Tests have also been conducted to determine if the new coolant would have any adverse effects on the uranium recycle systems. Experiments were scientifically designed after observation of the production operations so that accurate response to the immediate production concerns cou… more
Date: May 1983
Creator: Duerksen, W. K. & Taylor, P. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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