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 Decade: 1960-1969
 Year: 1961
 Collection: Technical Report Archive and Image Library
Idaho Division Summary Report

Idaho Division Summary Report

Date: 1961
Creator: Novick, Meyer & Thalgott, F. W.
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.
Contributing Partner: UNT Libraries Government Documents Department
Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor

Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor

Date: April 1961
Creator: Hanford Works
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.
Contributing Partner: UNT Libraries Government Documents Department
The Thermal Hydraulics Laboratory at Hanford

The Thermal Hydraulics Laboratory at Hanford

Date: November 1961
Creator: Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
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.
Contributing Partner: UNT Libraries Government Documents Department
Interim Report on Corrosion by Zirconium-Base Fluorides

Interim Report on Corrosion by Zirconium-Base Fluorides

Date: January 17, 1961
Creator: Adamson, G. M.; Crouse, R. S. & Manly, W. D.
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.
Contributing Partner: UNT Libraries Government Documents Department
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H

Date: March 1961
Creator: Sharp, R. E.
Description: Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.
Contributing Partner: UNT Libraries Government Documents Department
The RBU Reactor-Burnup Code: Formulation and Operation Procedures

The RBU Reactor-Burnup Code: Formulation and Operation Procedures

Date: July 1961
Creator: Triplett, J. R.; Merrill, E. T. & Burr, J. R.
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.
Contributing Partner: UNT Libraries Government Documents Department
Conceptual design of an in-pile package loop for sodium-cooled thermal reactor fuel testing

Conceptual design of an in-pile package loop for sodium-cooled thermal reactor fuel testing

Date: September 15, 1961
Creator: Blessing, W. G.
Description: Report issued by the APDA over a design study "of a facility for testing sodium-cooled thermal reactor fuel assemblies in the Advanced Test Reactor" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Contributing Partner: UNT Libraries Government Documents Department
Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

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

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.
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.
Contributing Partner: UNT Libraries Government Documents Department
Removal of Sodium from Core Subassemblies with White Oil and Ultrasonics

Removal of Sodium from Core Subassemblies with White Oil and Ultrasonics

Date: 1961
Creator: Kanaan, Z. R. & Nash, C. R.
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.
Contributing Partner: UNT Libraries Government Documents Department
Summary of the APDA Fuel Development Programs

Summary of the APDA Fuel Development Programs

Date: April 1961
Creator: Blessing, W. G.; Busch, J. S.; Duffy, J. G.; Hennig, R. J.; Jens, W. H.; Knight, F. W. et al.
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.
Contributing Partner: UNT Libraries Government Documents Department
A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter

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

Date: March 1961
Creator: Yaggee, F. L.
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.
Contributing Partner: UNT Libraries Government Documents Department
Corn Pone: A Multigroup, Multiregion Reactor Code

Corn Pone: A Multigroup, Multiregion Reactor Code

Date: 1961?
Creator: Kinney, W. E. & Coveyou, R. R.
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.
Contributing Partner: UNT Libraries Government Documents Department
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
Design and Hazards Summary Report Boiling Reactor Experiment V (BORAX V)

Design and Hazards Summary Report Boiling Reactor Experiment V (BORAX V)

Date: May 1961
Creator: Argonne National Laboratory
Description: Report describing the design and usage of the BORAX V nuclear reactor, its surrounding facility, systems, experimental programs, and possible hazards.
Contributing Partner: UNT Libraries Government Documents Department
Hazard Evaluation Report on the Fast Reactor Zero Power Experiment ZPR-III

Hazard Evaluation Report on the Fast Reactor Zero Power Experiment ZPR-III

Date: October 1961
Creator: Long, J. K.; McVean, R. L.; Thalgott, F. W. & Novick, M.
Description: Report documenting the fast zero power reactor experiment (ZPRG-III). This includes a description of the experiment and the reactor, hazards, and accidents.
Contributing Partner: UNT Libraries Government Documents Department
Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam

Corrosion Studies of Ternary Zirconium Alloys in High-Temperature Water and Steam

Date: July 1961
Creator: Misch, R. D. & Van Drunen, C.
Description: Report concerning the corrosion of several ternary zirconium alloys using distilled water at 350 degrees Celsius or ssteam heated to 540 degrees Celsius and 600 psi.
Contributing Partner: UNT Libraries Government Documents Department
EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations

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

Date: February 1961
Creator: Koch, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
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.)
Contributing Partner: UNT Libraries Government Documents Department
An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters

An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters

Date: October 1961
Creator: Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
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.
Contributing Partner: UNT Libraries Government Documents Department
An Ultrasonic Measurement System for The Precise Determination of the Elastic Moduli of Single Crystals

An Ultrasonic Measurement System for The Precise Determination of the Elastic Moduli of Single Crystals

Date: May 1961
Creator: Renken, C. J.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Uranium-Bismuth In-Pile Corrosion Test Loop: Radiation Loop No. 1

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

Date: May 1961
Creator: Waide, C. H.; Kukacka, L. E.; Meyer, R. A.; Milau, J.; Klein, J. H.; Chow, J. G. Y. et al.
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.
Contributing Partner: UNT Libraries Government Documents Department
A Review of the Utilization of Fission Fragment Energy for the Fixation of Nitrogen

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

Date: January 17, 1961
Creator: Steinberg, Meyer; Powell, J. R. & Green, Leon
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.
Contributing Partner: UNT Libraries Government Documents Department
Brookhaven National Laboratory Annual Report: July 1, 1960

Brookhaven National Laboratory Annual Report: July 1, 1960

Date: April 1961
Creator: Brookhaven National Laboratory
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.
Contributing Partner: UNT Libraries Government Documents Department
Nuclear Superheat Quarterly Project Report: Seventh Quarter, January-March 1961

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

Date: September 1961
Creator: Pennington, R. T.
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."
Contributing Partner: UNT Libraries Government Documents Department
Nuclear Superheat Quarterly Project Report: Sixth Quarter, October-December 1960

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

Date: November 1961
Creator: Pennington, R. T.
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."
Contributing Partner: UNT Libraries Government Documents Department
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