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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: Argonne National Laboratory Reports
 Collection: Technical Report Archive and Image Library
Design of the Argonne Low Power Reactor (ALPR)

Design of the Argonne Low Power Reactor (ALPR)

Date: May 1961
Creator: Hamer, E. E.; Grant, N. R.; Hooker, H. H.; Jorgensen, G. L.; Kann, W. J.; Lipinski, W. C. et al
Description: Report containing "[a] description (...) of the design of a prototype "packaged" nuclear power plant. The purpose of the plant is to alleviate fuel oil logistics and storage problems posed by remote auxiliary DEW Line radar stations north of the Arctic Circle. The ALPR (redesignated SL-1) is a 3 Mwt, heterogeneous, highly enriched uranium- fueled, natural-circulation boiling water reactor, cooled and moderated with light water. Steam at 300 psig, dry and saturated (421 deg F) is passed directly from the reactor to a conventional turbine-generator to produce electric power (300 kw nominal) and space-heating (400 kw) requirements consistent with rigid mechanical and structural specifications prescribed by the military, and dictated by the extreme geophysics prevailing at the ultimate site. The over-all design criteria emphasize: simplicity and reliability of operation and maintenance, with minimum supervision; minimum on-site construction; maximum use of standard components; limited water supply; utilization of local gravel for biological shielding; transportability by air lift; and nominal 3-year fuel operating lifetime per core loading." (p. 15)
Contributing Partner: UNT Libraries Government Documents Department
Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

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

Date: April 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.
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)
Contributing Partner: UNT Libraries Government Documents Department
Development of Techniques for Fabrication of Small-Diameter Thin-Wall Tungsten Tubing: Interim Progress Report covering the period from July 1, 1963 through December 31, 1963

Development of Techniques for Fabrication of Small-Diameter Thin-Wall Tungsten Tubing: Interim Progress Report covering the period from July 1, 1963 through December 31, 1963

Date: 1964
Creator: Burt, W. R., Jr.; Katiyar, H. C. & Mayfield, R. M.
Description: Report describing the methods and equipment used to extrude tungsten tubing from various starting materials.
Contributing Partner: UNT Libraries Government Documents Department
Five-year climatological summary, July 1949-June 1954, Argonne National Laboratory, DuPage County, Illinois

Five-year climatological summary, July 1949-June 1954, Argonne National Laboratory, DuPage County, Illinois

Date: 1954
Creator: Moses, Harry, 1916-2004 & Willett, Jack H.
Description: Report documenting various meteorological measurements for the purpose of understanding the possible dispersion of radioactive material.
Contributing Partner: UNT Libraries Government Documents Department
Calculations on U235 Fission Product Decay Chains

Calculations on U235 Fission Product Decay Chains

Date: May 1952
Creator: Faller, I. L.
Description: Report of equations for calculating decay of U235. The introduction states" Calculations have been made on the U235 fission product decay schemes. The results for a typical example, that of a reactor operating at 1000 kilowatts for 180 days, have been tabulated and graphed. General formulae have been used so that the results can be applied for any power level and any time of irradiation" (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
Spectral representation and criticality problem of a two-region cell transport operator

Spectral representation and criticality problem of a two-region cell transport operator

Date: 1965
Creator: Pollack, Israel
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Engineering development of fluid-bed fluoride volatility processes

Engineering development of fluid-bed fluoride volatility processes

Date: 1964
Creator: Vogel, G. J.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Engineering Properties of Diphenyl

Engineering Properties of Diphenyl

Date: August 11, 1953
Creator: Anderson, Kermit
Description: Report issued by the Argonne National Laboratory discussing engineering properties of diphenyl. As stated in the abstract, "data collected from the literature on the vapor pressure, enthalpy, liquid density, and vapor density of pure diphenyl are presented. A Mollier diagram, a temperature entropy diagram, and data on viscosity of diphenyl as a function of temperature are also presented" (p. 5). This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
Summary of Conference on the Toxicity of Carbon 14 Held at Argonne National Laboratory, January 15-16, 1952

Summary of Conference on the Toxicity of Carbon 14 Held at Argonne National Laboratory, January 15-16, 1952

Date: March 1952
Creator: Brues, A. M.
Description: Report issued by the Argonne National Laboratory discussing the Conference on the Toxicity of Carbon 14. At the outset of the meeting it was emphasized that the group was brought together to discuss work which had a bearing on the toxicity of C14 compounds used either clinically or industrially, and the hope was expressed that the group might be able to reach some conclusions on these matters. This report includes tables.
Contributing Partner: UNT Libraries Government Documents Department
Progress Report on the Argonne-Oak Ridge Digital Computer

Progress Report on the Argonne-Oak Ridge Digital Computer

Date: March 5, 1951
Creator: Birge, W. A.
Description: Report issued by the Argonne National Laboratory discussing a progress report on the Argonne-Oak Ridge digital computer. This report is an interim report, whose primary value is that it has forced those engaged in the work to give concrete expression to what they have been doing and thinking about up to this point. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department