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Idaho Division Summary Report

Description: Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations.
Date: 1961
Creator: Novick, Meyer & Thalgott, F. W.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor

Description: Report evaluating "the effects of nuclear steam superheating, as utilized in the Russian design, on the economics of electric power production, assuming the use of such a design in the United States" (p. 1). This report includes a description of the Beloyarsk Station and modifications made to the Russian designs for use in the United States.
Date: April 1961
Creator: Hanford Works
Item Type: Report
Partner: UNT Libraries Government Documents Department

The Thermal Hydraulics Laboratory at Hanford

Description: Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Date: November 1961
Creator: Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Interim Report on Corrosion by Zirconium-Base Fluorides

Description: Report issued by the Oak Ridge National Laboratory discussing studies conducted on corrosion by fluorides. Equipment, procedures, results, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: January 17, 1961
Creator: Adamson, G. M.; Crouse, R. S. & Manly, W. D.
Item Type: Report
Partner: UNT Libraries Government Documents Department

The RBU Reactor-Burnup Code: Formulation and Operation Procedures

Description: Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.
Date: July 1961
Creator: Triplett, J. R.; Merrill, E. T. & Burr, J. R.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Description: Report issued by the APDA over a design study conducted on an "in-pile package loop for use as a reactor fuel test facility" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Date: July 28, 1961
Creator: Blessing, W. G.; Balsbaugh, R. R.; Bloomfield, D. E.; Busch, J. S.; Hennig, R. J.; Jens, W. H. et al.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Removal of Sodium from Core Subassemblies with White Oil and Ultrasonics

Description: Report issued by the APDA over methods "for removing sodium from fuel and blanket sub-assemblies that have been irradiated in the reactor of the Enrico Fermi Atomic Power Plant" (p. 3). The cleaning methods are described, as well as experimental studies conducted on them. This report includes illustrations, and photographs.
Date: 1961
Creator: Kanaan, Z. R. & Nash, C. R.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Summary of the APDA Fuel Development Programs

Description: Report issued by the APDA over fuel development programs. Designs for fast breeder reactors, safety tests, and methods are presented and discussed. This report includes tables, illustrations, and photographs.
Date: April 1961
Creator: Blessing, W. G.; Busch, J. S.; Duffy, J. G.; Hennig, R. J.; Jens, W. H.; Knight, F. W. et al.
Item Type: Report
Partner: UNT Libraries Government Documents Department

A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter

Description: Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Date: March 1961
Creator: Yaggee, F. L.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Corn Pone: A Multigroup, Multiregion Reactor Code

Description: Report covering the development of a set of difference equations for machine solution. In addition, this report serves as user's manual for Corn Pone, which is a code for the Oracle, the Oak Ridge National Laboratory computer.
Date: 1961?
Creator: Kinney, W. E. & Coveyou, R. R.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Design of the Argonne Low Power Reactor (ALPR)

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)
Date: May 1961
Creator: Hamer, E. E.; Grant, N. R.; Hooker, H. H.; Jorgensen, G. L.; Kann, W. J.; Lipinski, W. C. et al.
Item Type: Report
Partner: UNT Libraries Government Documents Department

EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations

Description: Report containing zero power (<1 kw) Dry Critical Experiments that were "to be conducted in the EBR-II Reactor prior to filling the Primary System with sodium coolant" (p. 7.) The two primary objectives of these experiments were to determine how well the system performed without sodium coolant and to "determine and/or verify certain operational data to permit modification or improvement of the system (neutron shield, instrumentation, etc.) prior to the introduction of sodium into the system" (p. 7.)
Date: February 1961
Creator: Koch, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Item Type: Report
Partner: UNT Libraries Government Documents Department

An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters

Description: Report estimating the merits of a variety of nuclear reactor concepts for use as external superheaters to be added on to a steam-producing nuclear power plant.
Date: October 1961
Creator: Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Uranium-Bismuth In-Pile Corrosion Test Loop: Radiation Loop No. 1

Description: Report issued by the Brookhaven National Laboratory discussing uranium-bismuth corrosion test loops. Design, construction, and operation of the test loops are presented. This report includes tables, illustrations, and photographs.
Date: May 1961
Creator: Waide, C. H.; Kukacka, L. E.; Meyer, R. A.; Milau, J.; Klein, J. H.; Chow, J. G. Y. et al.
Item Type: Report
Partner: UNT Libraries Government Documents Department

A Review of the Utilization of Fission Fragment Energy for the Fixation of Nitrogen

Description: Report issued by the Brookhaven National Laboratory discussing methods of nitrogen fixation, and their economic impacts. As stated in the introduction, "studies are described on circulating dust fuels, as well as fixed plated, porous bed, and other types of fuels as the basis for chemo-nuclear reactor designs, and the various fuel systems are compared on a technical and economic basis" (p. 3). This report includes tables, and illustrations.
Date: January 17, 1961
Creator: Steinberg, Meyer; Powell, J. R. & Green, Leon
Item Type: Report
Partner: UNT Libraries Government Documents Department

Brookhaven National Laboratory Annual Report: July 1, 1960

Description: Report issued by the Brookhaven National Laboratory discussing the work conducted by the lab during the fiscal year of 1960. As stated in the introduction, "the progress and trends of the research program are presented together with a description of the operational, service, and administrative activities of the Laboratory" (p. vii). This report includes tables, illustrations, and photographs.
Date: April 1961
Creator: Brookhaven National Laboratory
Item Type: Report
Partner: UNT Libraries Government Documents Department

Nuclear Superheat Quarterly Project Report: Seventh Quarter, January-March 1961

Description: From introduction: "This is the seventh of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: September 1961
Creator: Pennington, R. T.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Nuclear Superheat Quarterly Project Report: Sixth Quarter, October-December 1960

Description: From introduction: "This is the sixth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: November 1961
Creator: Pennington, R. T.
Item Type: Report
Partner: UNT Libraries Government Documents Department

Fabrication of Fuel Rods by Tandem Rolling

Description: From introduction: "The purpose of this report is to present the details of the exploratory and developmental work on tandem rolling, and the subsequent fabrication of tandem rolled fuel rods for irradiation testing in the Vallecitos Boiling Water Reactor."
Date: July 1961
Creator: Lingafelter, J. W.
Item Type: Report
Partner: UNT Libraries Government Documents Department