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Final Summary Safeguards Report For The General Electric Test Reactor

Description: This report is submitted to the U. S. Atomic Energy Commission as a final summary safeguards and hazards evaluation of a proposed test reactor at its Vallecitos Atomic Laboratory in Alameda County of California. It is the purpose of this report to provide sufficient data to obtain an AEC facility license for the reactor.
Date: February 20, 1958
Creator: Andersen, R. K. & Jacobs, I. M.
Partner: UNT Libraries Government Documents Department
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Fuel Failure Examinations and Analyses in the High Power Density Program

Description: Summary: The High Power Density Project includes a comprehensive fuel development program which has the objective of developing and demonstrating the performance of a nuclear reactor core having a high power density, long fuel life, and low fabrication cost. The fuel program is made up of two principal tasks. Task 1A consists of irradiation tests in the VBWR of Type 304 stainless steel clad, UO2 pellet type fuel rods fabricated by current commercial processes. Task 1B consists of the investigat… more
Date: September 16, 1963
Creator: Arlt, W. H. & Vandenberg, S. R.
Partner: UNT Libraries Government Documents Department
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Enclosure Pressure Calculation Method

Description: A method of determining enclosure pressure in the event of a reactor rupture is presented and a sample calculation is shown. This method was used in calculating the design pressure of the Dresden Nuclear Power Station enclosure.
Date: October 6, 1956
Creator: Bailey, J. A.
Partner: UNT Libraries Government Documents Department
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N. S. Savannah Fuel Design and Development Program: Fuel Rod Vibration (Preliminary Report)

Description: This is a preliminary report on the investigation of the N.S. Savannah replacement fuel rod vibration amplitude when excited by water flowing parallel to the axis of the fuel rod. Methods of calculating the fuel rod frequency in air were verified by experiment. Work is continuing to establish the validity of methods of calculating natural frequencies in water and to confirm the correlation of flow induced vibration amplitude found in reference (1).
Date: September 25, 1959
Creator: Bailey, J. A. & Shields, C. M.
Partner: UNT Libraries Government Documents Department
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Design and Fabrication of Coextruded Stainless Steel Clad UO2 Fuel Rods

Description: A process was developed in which stainless steel-clad UO2 fuel rods are fabricated by high-temperature coextrusion. The process has a potential of being a more economical method for the preparation of stainless steel-clad UO2 fuel rods than the conventional pellet process. Consequently, it was considered advantageous to evaluate the irradiation characteristics of fuel rods fabricated in this manner. Therefore, 24 coextruded fuel rods were manufactured for evaluation in a reactor. The required a… more
Date: June 1963
Creator: Baroch, C. J.
Partner: UNT Libraries Government Documents Department
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Physics Calculations for the Consumers Big Rock Point Process Computer

Description: The physics calculations to be performed on the Consumers On-Line Process Computer are reported. As a result of these calculations, a three-dimensional power shape is simulated, a reactivity balance is approximated, and the neutron exposure of each third of fuel bundle and control rod are accumulated. The work was reported as a part of the Consumers Research and Development Program.
Date: May 1963
Creator: Barth, N. H.
Partner: UNT Libraries Government Documents Department
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The Development of a Scheduling Computer For The Big Rock Plant

Description: The basic work for development of a scheduling computer for the Consumers' Big Rock Plant is outlined in this report. The computer's purpose is to make feasible higher power densities by operation closer to fuel element burnout limits, and to maximize fuel burnup.
Date: 1961
Creator: Beckjord, Eric S.
Partner: UNT Libraries Government Documents Department
open access

Compact Control Rod Drive Study For a Boiling Water Reactor in a T7 Tanker

Description: The reason for initiating the compact drive study for the T7 tanker was to investigate control rod drive size, location, and removal space requirement factors and select the control rod drive mechanism which would allow optimization of the over-all size of the containment vessel. Approximately twelve mechanical/hydraulic control rod drive arrangements were considered during this study.
Date: August 8, 1960
Creator: Biglieri, N. J.
Partner: UNT Libraries Government Documents Department
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Experimental Investigations of the Removal of Sodium Oxide From Liquid Sodium

Description: Experimental investigations were conducted to obtain additional information on the growth and characteristics of sodium oxide deposits in liquid sodium which could lead to system plugging. These investigations included the removal of sodium oxide from molten sodium by the cold trap method.
Date: January 18, 1960
Creator: Billuris, G.
Partner: UNT Libraries Government Documents Department
open access

Reactor Pressure Vessel Material Surveillance Program at the Garigliano Nuclear Power Plant

Description: Abstract: A materials exposure program has been established in the Garigliano Nuclear Power Plant to measure the effect of neutron irradiation and time at temperate on the mechanical properties of the reactor pressure vessel steel. Base metal specimens were made from portions of the pressure vessel steel, and weld heat-affected zone and weld metal samples were taken from a weldment made from the pressure vessel steel and simulating a pressure vessel circumferential weld since there are no longi… more
Date: March 1964
Creator: Brandt, F. A. & Kobsa, I. R.
Partner: UNT Libraries Government Documents Department
open access

Compilation of Techniques Used By Vallecitos Radioactive Materials Laboratory

Description: Equipment and techniques for remote examination of irradiated fuel assemblies applicable to the Maritime Program are described. The following subjects are covered: visual and photographic examination, dimensional measurements, gamma activity scanning, fission gas release and fuel rod void volume determinations, density measurements, metallographic examination, and radiochemical burnup analysis.
Date: February 1961
Creator: Brandt, F. A.; Mathay, P. W. & Zimmerman, D. L.
Partner: UNT Libraries Government Documents Department
open access

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Tenth Quarterly Report, January-March 1964

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program. Information is reported on vented fuel production, transient testing of fuel, fuel performance evaluation, fast-flux irradiation of fuel, and reactor physics and core analysis.
Date: April 1964
Creator: Breizy, C. E.
Partner: UNT Libraries Government Documents Department
open access

Swaging Over Unground Pellets

Description: This study was designed to determine how swaging stainless steel over unground pellets will affect the integrity of fuel rods, and to find maximum pellet diameter variation that can be tolerated.
Date: January 25, 1961
Creator: Brown, R. L.
Partner: UNT Libraries Government Documents Department
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Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Program Summary and Sixth Quarterly Report, July 1 - September 30, 1962

Description: The work described in this report represents progress toward an agreement signed by the United States and the European Atomic Energy Community which provides a basis for cooperation in programs for the advancement of peaceful applications of atomic energy.
Date: October 15, 1962
Creator: Carver, J. G.; Lagache, M. P. & Morgan, W. R.
Partner: UNT Libraries Government Documents Department
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Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors Quarterly Report For Period April 1 - June 30, 1962

Description: The Program fuel element has continued under irradiation in the Vallecitos Boiling Water Reactor, thermal energy group transfer cross sections for UO2 have been computed, and data have been reduced from the resonance wire activations performed last quarter. Future plans are included.
Date: July 15, 1962
Creator: Carver, J. G.; Morgan, W. R. & Robkin, M. A.
Partner: UNT Libraries Government Documents Department
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Preoperational Power Stability Analysis of the Consumers Big Rock Point Plant

Description: Summary: An analytical study of the stability of the Big Rock Nuclear Reactor has been performed for the plant as built, and supplements a previous design stability study. The plant has been determined by this analysis to be very stable under every mode of operation anticipated during Phase I of the development program testing. Even under conservative assumptions of system parameters the minimum calculated gain and phase margins do not go below 13.0 db and 46 degrees, respectively. (Nor are … more
Date: February 1964
Creator: Case, J. M.
Partner: UNT Libraries Government Documents Department
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Consumers Big Rock Point Nuclear Power Reactor Stability Analysis

Description: This report presents the results of an analysis which was undertaken to investigate the power stability of the Consumers Big Rock Point Nuclear Power Reactor.
Date: 1964?
Creator: Case, J. M. & Holland, L. K.
Partner: UNT Libraries Government Documents Department
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Reactor Safety and Fuel Cycle Economics Considerations for Fast Reactors

Description: Abstract: A core design study of a 10 Mwe fast ceramic reactor is presented. Local reactivity coefficients, safety criteria, accident analyses, and economics are considered. An attempt is made to find a new balance of characteristics by purely geometric devices, i.e., by exploring the sodium : fuel ratio and varying the height : diameter ratio of the core. The use of BeO in the core was also investigated.
Date: November 11, 1963
Creator: Cohen, K. P.; Greebler, P.; McNelly, M. J.; Murphy, P. M.; Sherer, D. B. & Zebroski, E. L.
Partner: UNT Libraries Government Documents Department
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Amendment No. 1 to Preliminary Hazards Summary Report For The Dresden Nuclear Power Station

Description: Commonwealth Edison Company for the purpose of supplementing the license application for the Dresden Nuclear Power Station submits herewith Amendment No.1 to the portion of the Final Hazards Summary Report entitled Preliminary Hazards Summary Report.
Date: May 26, 1958
Creator: Commonwealth Edison Company
Partner: UNT Libraries Government Documents Department
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Amendment No. 4 to Hazards Summary Report For The Dresden Nuclear Power Station

Description: This report is an amendment to the Preliminary Hazards Summary Report (1) and the Operating Procedures and Emergency Plans (5) for the Dresden Nuclear Power Station, submitted to the United States Atomic Energy Commission on September 3, 1957, and June 5, 1958, respectively.
Date: February 6, 1959
Creator: Commonwealth Edison Company
Partner: UNT Libraries Government Documents Department
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