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Chemistry Research and Development. Progress Report, July 1977--April 1978

Description: The following studies are reported on: calorimetry and thermodynamics of nuclear materials; actinide recovery and purification; optimization of the cation exchange process for recovering americium and plutonium from molten salt extraction residues; decontamination of soil; secondary actinide recovery; evaluation of tributyl phosphate-impregnated sorbent for plutonium-uranium separations; comparison of cation exchange recovery of actinides from the NaCl--KCl--MgCl/sub 2/ and CaCl/sub 2/--KCl--Mg… more
Date: November 8, 1978
Creator: Miner, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Simulations of NSTX with a Liquid Lithium Divertor Module

Description: The UEDGE edge plasma transport code is used to model the effect of the reduced recycling provided by the Liquid Lithium Divertor (LLD) module that will be installed in NSTX. UEDGE's transport coefficients are calibrated against an existing NSTX shot using midplane and divertor diagnostic data. The LLD is then incorporated into the simulations as a reduction in the recycling coefficient over the outer divertor. Heat transfer calculations performed using the resulting heat flux profiles indicate… more
Date: July 8, 2008
Creator: D. P. Stotler, R. Maingi, H.W. Kugel, A. Yu. Pigarov, T.D. Rognlien, V.A. Soukhanovskii
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Bench-Scale Co-Processing

Description: This topical report is the first for the UOP Bench-Scale Co-processing contract. The objective of this contract is to extend and optimize the UOP single-stage, slurry-catalyzed co-processing scheme. UOP co-processing uses a single-stage, slurry-catalyzed scheme in which petroleum vacuum resid and coal are simultaneously upgraded to a high-quality synthetic oil. A highly active, well-dispersed catalyst permits operations at moderate- and high-severity reaction conditions with minimum detrimental… more
Date: November 8, 1993
Creator: Piasecki, C. A.; Gatsis, J. G. & Fullerton, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: January 1 - March 31, 1963.

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. All program efforts have been temporarily deferred except for those associated with the irradiation of the program fuel element in the VBWR. The program fuel element was exposed to a burnup of 465 MWD/T during the quarter which brings the to… more
Date: April 8, 1963
Creator: Robkin, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bench-scale co-processing. Quarterly report No. 9, March 1, 1990--June 31, 1990

Description: This is the ninth quarterly report. Objective is to extend and optimize UOP`s single-stage slurry-catalyzed co-processing scheme. Emphasis is given to defining and improving catalyst utilization and costs, evaluating alternative and disposable slurry-catalyst systems, and improving catalyst recycle and recovery. During this quarter, a temperature survey was completed with the reference V catalyst and liquid recycle. Objective of this study was to determine whether the improved high-severity per… more
Date: October 8, 1990
Creator: Piasecki, C. A.; Gatsis, J. G.; Liu, L. L.; Lea, C. L. & Miller, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production of ``X`` buttons in the 234-5 Building

Description: Since 1945 the routine production of plutonium (``A`` buttons) at Atomic Energy plants has been accomplished by heating mixtures of plutonium tetrafluoride, calcium and iodine in crucible-bomb assemblies. Yields above 97% and metal of adequate purity are consistently obtained by this process. Plutonium (``X`` button) production has also been carried out routinely by including plutonium turnings with the powder mixture given above. A majority (several thousand) of buttons produced in the 234-5 B… more
Date: April 8, 1952
Creator: Collins, P.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Volumetric Radioactivity Viewed as Surface Radioactivity for Free Release Assessment Purposes

Description: As a part of the SRS Beneficial Reuse Program, stainless steel radioactive scrap metal is melted, pour into ingots, and roll into sheets. The sheets are then fabricated into boxes and barrels for beneficial reuse. The melting activity is a partial decontamination process. Certain isotopes separate from the melted steel, while others stay in solution. Cobalt-60 is the primary constituent, which remains in solution, and becomes the major contributor to the volumetric radioactivity of the finished… more
Date: July 8, 1998
Creator: Boettinger, W.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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