Search Results

MINIMIZER: A Computer Code for Determining Minimum Fuel Cost

Description: Report that describes the Hanford Laboratories MINIMIZER code and demonstrates its accuracy in providing fissile fuel costs in a precise and automatic manner.
Date: July 1965
Creator: Eschbach, E. A.; Deonigi, D. E. & McConiga, A. F.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Pressure-Pulse Propagation in Two-Phase One- and Two-Component Mixtures

Description: Report issued by the Argonne National Laboratory discussing the propagation velocity of pressure pulses in two-phase mixtures. As stated in the abstract, "in this study, a comprehensive analytical development of the propagation velocity of small pressure pulses is presented for bubble, annular, stratified, droplet, and slug-flow regimes. Particular attention is given to the influence of flow regime on the momentum transfer between phases" (p. 9). This report includes tables, illustrations, and a photograph.
Date: March 1971
Creator: Henry, R. E.; Grolmes, M. A. & Fauske, H. K.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Heat Transfer in an Annulus with Asymmetric Heating

Description: Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).
Date: February 1959
Creator: Lisin, Alexander Vladimir; Mackewicz, W. B. & Reynolds, William C., 1933-2004
Item Type: Report
Partner: UNT Libraries Government Documents Department

Casting and Fabrication of Core Material For Argonne Low Power Reactor Fuel Elements

Description: Report issued by the Argonne National Laboratory over studies conducted on the Argonne Low Power Reactor. As stated in the abstract, "this report describes the manufacture of 1150 fuel core blanks, of which 816 were used in the fabrication of fuel elements. Development, casting, hot and cold rolling, cleaning, and punching of core blanks are discussed, as are nondestructive testing and evaluation of the manufacturing processes" (p. 7). This report includes tables, illustrations, and photographs.
Date: December 1959
Creator: Salley, R. L. & Burt, W. R., Jr.
Item Type: Report
Partner: UNT Libraries Government Documents Department

PRTR second generation shim assembly

Description: From introduction: "This document discusses the design, fabrication, assembly, and testing of a second generation shim rod assembly, and testing of a second generation shim rod assembly prototype for use in the Plutonium Recycle Test Reactor."
Date: November 1964
Creator: Rasmussen, D. E.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

Description: Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.
Date: October 1964
Creator: Swanberg, F.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Fast Reactor Core Design Parameter Study

Description: Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.
Date: March 1960
Creator: Atomic Power Development Associates
Item Type: Report
Partner: UNT Libraries Government Documents Department

The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements

Description: "The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr" (p. iii).
Date: 1959
Creator: Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Item Type: Report
Partner: UNT Libraries Government Documents Department

An Analytical Study of the Feasibility of Irradiating U233/Th232 Metal Fuel Experiments in EBR-II

Description: Recent concerns about the proliferation and diversion of plutonium have lead to reconsideration of Uranium-233/Thorium-232 fuel cycles. Although thorium fuels have been studied earlier, much of that work is incomplete; consequently, additional irradiation studies will be necessary.
Date: 1979?
Creator: Foltman, A. J. & Meneghetti, D.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Monte Carlo-Based Validation of the ENDF/MC²-II/SDX Cell Homogenization Path

Description: The results are presented of a program of validation of the unit cell homogenization prescriptions and codes used for the analysis of Zero Power Reactor (ZPR) fast breeder reactor critical experiments. The ZPR drawer loading patterns comprise both plate type and pin-calandria type unit cells. A prescription is used to convert the three dimensional physical geometry of the drawer loadings into one dimensional calculational models. The ETOE-II/MC²-II/SDX code sequence is used to transform ENDF/B basic nuclear data into unit cell average broad group cross sections based on the 1D models. Cell average, broad group anisotropic diffusion coefficients are generated using the methods of Benoist or of Gelbard. The resulting broad (approx. 10 to 30) group parameters are used in multigroup diffusion and S(su n) transport calculations of full core XY or RZ models which employ smeared atom densities to represent the contents of the unit cells.
Date: April 1979
Creator: Wade, D. C.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Fuel Cycle Programs, Quarterly Progress Report: July-September 1978

Description: Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research. Fuel cycle work reported for this period includes testing of hydraulic performance and extraction efficiency of eight-stage centrifugal contactors, testing of a flowsheet for the Aralex process, evaluation of ruthenium and zirconium extraction in a miniature centrifugal contactor, study of zirconium aging in the organic phase and its effect on zirconium extraction and hydraulic testing of the 9-cm-ID contactor.
Date: January 1980
Creator: Steindler, M. J.; Ader, M.; Bernstein, G.; Flynn, K.; Gerding, T.; Jardine, L. J. et al.
Item Type: Report
Partner: UNT Libraries Government Documents Department

The Status and Development Potential of Plate-Type Fuels for Research and Test Reactors

Description: A program of transient in-reactor experiments is being conducted by Argonne National Laboratory in the Transient Reactor Test (TREAT) facility to guide and support analyses of hypothetical core-disruptive accidents (HCDA) in liquid-metal fast breeder reactors (LMFBR). Test results provide data needed to establish the response of LMFBR cores to hypothetical accidents producing fuel failure, coolant boiling, and the movement of coolant, molten fuel, and molten cladding. These data include margins to fuel failure, the modes of failure and movements, and evidence for identification of the mechanisms which determine the failure and movements. A key element in the program is the fast-neutron hodoscope, which detects fuel movement as a function of time during experiments.
Date: March 1979
Creator: Stahl, D.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Leaching Action of EJ-13 Water on Unirradiated UO₂ Surfaces under Unsaturated Conditions at 90 C : Interim Report

Description: A set of experiments, based on the application of the Unsaturated Test method to the reaction of uranium dioxide with EJ-13 water, has been conducted over a period of 182.5 weeks. One half of the experiments have been terminated, while one half are still ongoing. Solutions that have dripped from uranium dioxide specimens have been analyzed for all experiments, while the reacted uranium dioxide surfaces have been examined for only the terminated experiments. A pulse of uranium release from the uranium dioxide solid, in conjunction with the formation of dehydrated schoepite on the surface of the uranium dioxide, was observed during the 39- to 96-week period. Thereafter, the uranium release decreased and a second set of secondary phases was observed. The latter phases incorporate cations from the EJ-13 water and include boltwoodite, uranophane, sklodowskite, compreignacite, and schoepite. The experiments are being continued to monitor for additional changes in solution composition and secondary phase formation, and have now reached the 319-week period.
Date: July 1991
Creator: Wronkiewicz, D. J.; Bates, John K.; Gerding, Thomas J.; Veleckis, Ewald; Tani, B. & Hoh, J. C.
Item Type: Report
Partner: UNT Libraries Government Documents Department