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Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW

Description: From Introduction: "This hazards report covers the basic modifications to the EBWR plant as designed to increase the present operating design rating of 20 Mwt to a new rating of 100 Mwt. it is written as a supplement to ANL-5781 (the original hazards report) and follows the outline of that report for purposes of cross reference."
Date: October 1960
Creator: Wimunc, E. A. & Harrer, J. M.

Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Description: Report regarding "[t]he Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyro-metallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5 percent fissium and contains about 46 wt.% Uranium-235 . The blanket material consists of uranium in which plutonium is bred. Core and blanket subassemblies contained in transfer coffins are transferred between EBR-II and the Fuel Cycle Facility, which is in an adjacent building." (p. 13)
Date: April 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.

Status Report on the Argonne Advanced Research Reactor

Description: From Introduction: "This is a status report on the interim design and development for an advanced research reactor (AARR) that will produce a maximum thermal neutron flux of 5 x 10 to the fifteenth power neutrons/ (cm2) (sec). As a result, this report also contains sections covering shielding, plant layout, fuel charging, maintenance, and auxiliary facilities."
Date: November 1961
Creator: Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.

The Electrical Design of the EBR-II

Description: Report that "summarizes the electrical design of the Experimental Breeder Reactor II Facility (EBR-II). It attempts to gather together and present in reasonable detail the essential features and workings of the completed design, and to present a concise overall view of the system" (p. 11).
Date: June 1966
Creator: Verber, F. & Schmidt, H. L.

On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate

Description: From Introduction: "Specifically, we shall be concerned with the case of a solid right circular cylinder of infinite axial extent, having a stress-free outer boundary, being cooled by a temperature-independent boundary conductance, and having an axial heat-generation rate of form shown in Fig. 1. The inclusion of a radial dependence proportional to I^0(r/L) is only a minor complication in solving the required heat-transfer problem and, for reference, has been included in the solution for the temperature field to be found in Section II below."
Date: December 1966
Creator: Valentin, Richard A.

U.S. Participation in the OEEC Halden Reactor Project May 1959 to September 1960

Description: From Introduction: "This report summarizes the activities of the OEEC Halden Reactor Project, Halden, Norway, during the period of participation in the project by the author, from May 21, 1959 to September 22, 1960. The review is presented here in the interest of completeness of this report, in an effort to provide an impression of the character of research being carried out at Halden."
Date: December 1960
Creator: Fromm, Leonard W., Jr.

Two-Phase Heat Transfer With Gas Injection Through A Porous Boundary Surface

Description: From Introduction: "The purpose of this study is to investigate some of the hydrodyamic aspects of two-phase heat transfer in the lower quality range. The results of this study should contribute to a better and more thorough understanding of the processes and mechanisms affecting two-phase heat transfer, and in this way help in improving its prediction."
Date: March 1964
Creator: Kudirka, A. A.

A Liquid-Metal Heat-Transfer Experiment

Description: From Introduction: "The primary objective of the Boiling Liquid Metal Program in the Reactor Engineering Division at Argonne is to be obtain experimental information pertinent to the the boiling-heat transfer and fluid-flow behavior of the alkali metals, especially sodium."
Date: June 1965
Creator: Holtz, R. E.

Propagation of Density Disturbances in Air-Water Flow

Description: From Introduction: "In this work, a forced-circulation air-water loop was employed for investigating the behavior of void perturbations. Upon attaining steady-state conditions, disturbances in the void fraction were superimposed at very low frequencies (~0.4 cps). A better understanding of hydrodynamic transient behavior will generate more confidence in the design of boiling-water reactor systems."
Date: June 1965
Creator: Nassos, George P.