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Physics Performance of the EBWE in Its Zero to 100 Mw Operation

Description: The distribution of fuel elements in the EBWR core is described. Spike elements with boron steel strips were provided in the core for burnup allowance. A calibration of the control rod system with Zircaloy followers was made. Void coefficient measurements were made for two different H/sub 3/BO/sub 3/ concentrations. Power runs were made, and reactivity loss vs. power characteristic was obtained. Steam remaining in the core, or carryunder,'' was indicated. Some of the spikes were remov… more
Date: June 1963
Creator: Iskenderian, H. P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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NS Savannah Replacement Control Rod Drives Safeguards Report. Volume II. Description of System Modifications and Hazards Analysis

Description: Report discussing safeguards on operation of the NS Savannah with the replacement rod drive system. This volume includes a description of system modifications and a casualty analysis of the replacement drive system. Included is a description of the replacement control rod drive installation on the Savannah, the rod drive reliability, reactor control and rod program analysis, accident analysis, and a verification of analog computer results.
Date: October 1962
Creator: Wascher, Robert E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Report for SNAP 4: July-September 1961

Description: Report describing the program objectives, program summary, summary developments status, development system (critical assembly), and component development progress (fuel) for Systems for Nuclear Auxiliary Power (SNAP) 4, a multipurpose compact nuclear power system, for the period July to September 1961.
Date: December 15, 1961
Creator: Flower, L. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SRE-PEP Moderator Elements: Final Report

Description: Report discussing the design and engineering of the new Zircaoloy-2 moderator and reflector elements for the Solid Reactor Experiment (SRE) Power Expansion Program (PEP). The existing design, proposed design, and details of the final design are described. Additional aspects described include are material properties, thermal analysis, stress analysis, and the final proof test.
Date: January 15, 1966
Creator: Jones, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary SNAPSHOT-1 Performance Summary

Description: Report presenting the preliminary evaluation test results from the Space Nuclear Auxiliary Power Shot (SNAPSHOT) flight test, launched in April 3, 1965. A flight test description, discussion of the data system, test results, description of system shutdown, and identification of technology gained from the Systems for Nuclear Auxiliary Power (SNAP) 10A flight test are included.
Date: August 1, 1965
Creator: Galantine, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Retirement of the Sodium Reactor Experiment

Description: Report describing the Sodium Reactor Experiment (SRE) plan and post-operational programs. The SRE retirement program is described in detail together with an alternative plans that were considered. The current status of the plant is described and the means presented whereby the plan will be maintained in its present condition. The time and cost schedule to accomplish the retirement is included. Finally. recommendations are made that would be useful to future retirement efforts. (Abstract, p. 6)
Date: August 30, 1968
Creator: Eggleston, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SL-1 Annual Operating Report: February, 1960-January 3, [1961]

Description: The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
Date: June 15, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Development and Testing of UO2 Fuel Systems for Water Reactor Applications: Summary Report, July 1, 1961 - June 15, 1962

Description: From introduction: "The work described in this report represents the Joint United States - European Atomic Energy Community effort which is in keeping with the spirit of cooperation in contributing to the common good by the sharing of scientific and technical information and minimizing the duplication of effort by the limited pool of technical talent available in Western Europe and the United States."
Date: June 1962
Creator: Murtha, B. E. & Chernock, W. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study of SCTI Control System

Description: Introduction: This report has been prepared to document the extensive analytical work required to design the control system for the Sodium Components Test Installation (SCTI), constructed for the Atomic Energy Commission at the Atomics International field laboratory.
Date: December 1, 1964
Creator: Griffin, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Boiling Depressurization Transients

Description: Abstract: An analytical and experimental effort toward a better understanding of the mechanisms involved in nuclear power reactor loss-of-pressure accidents is presented.
Date: August 1, 1964
Creator: Halfen, F. J. & Berganzoli, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design for a Fast Flux Liquid Metal Loop in the Advanced Test Reactor

Description: The purpose of this document is to present criteria for the Titles I and II design of the Fast Flux Loop Facility which is to be a part of the Advanced Test Reactor. This facility is to be used for irradiation of fast reactor assemblies under simulated fast reactor operating conditions.
Date: July 1962
Creator: Babcock & Wilcox Company. Atomic Energy Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Device for Continuous Detection of Hydrogen in Sodium

Description: Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date: December 15, 1960
Creator: Strahl, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reduction of Liquid Radioactive Wastes to Solids: Scouting Tests

Description: Abstract: Scouting experiments indicated that calcination of highly active Darex and Sulfex decladding and Purex extraction wastes will not release hazardous amounts of fission products to the atmosphere. Simulated wastes containing up to 90 curies/liter or activity were evaporated and calcined to 750°C and the off-cases passed through a condenser and a series of caustic scrubbers. Less than 0.1% of the fission products was released, of which ruthenium was 10-90%. Fission product release was… more
Date: November 24, 1958
Creator: Hancher, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Reactor Project Quarterly Progress Report: June 1960

Description: Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. Design Investigations: The effects on the power distribuestablished. A mathematical model was developed for studying shifting of the coolant stream as it moves along a rod in order to predict the temperatures of the parallel streams as they progress through the reactor. A fuelelement life code developed for computing the internal temperature structure, the amount of fission g… more
Date: August 22, 1960
Creator: Oak Ridge National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project: Sixteenth Quarterly Progress Report, January-March 1964

Description: Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. Five tasks are in progress: (1) Task 1A-High Power Density Fuel Development, (2) Task 1B-Fuel Fabrication Development. Assembly, (3) Task II-Stability, Heat Transfer and Fluid Flow, (4) Task III-Physics Development, and (5) Task IV-Co-Ordination and Test Planning.
Date: April 1, 1964
Creator: Holladay, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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