Technical Report Archive & Image Library (TRAIL) - 56 Matching Results

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Consolidated Edision Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.
Date: July 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Control Rod Drive Line Testing

Description: The adequacy of the Consolidated Edison Thorium Reactor (CETR) control rod drive line operation was evaluated and proven by the development program described in this report. This program also included evaluation of materials and fabrication processes.
Date: August 1960
Creator: Good, J. A. & Thoren, D. E.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Control System Design

Description: The Consolidated Edison Thorium Reactor Control System has been designed to provide the operators with a reliable, safe and accurate means of controlling the plant. Manual and automatic positioning of control rods can be accomplished. The automatic plant controller has been designed to meet the design criteria under the representative CETR demanded load changes. Adaptability has been built into the plant controller by providing variable controller adjustments for variations in reactor charac… more
Date: August 1960
Creator: Carson, W. E.; Chubb, W. B.; Pickett, R. T. & Deddens, J. C.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor: Core Assembly Physics and Zero Power Tests Report

Description: Results of zero power tests to confirm the nuclear design of the Consolidated Edison Thorium Reactor Core are presented. The maximum core reactivity, control rod worths, and power distribution were measured.
Date: September 1961
Creator: Edlund, Milton C. (Milton Carl), 1924-; Ball, R. M.; Deddens, J. C. & Flickinger, R. F.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Critical Experiments with Oxide Fuel Pins

Description: This report describes the critical experiments with pin-type oxide fuel elements for the Consolidated Edison Thorium Reactor (CETR). This report also describes the measurements and gives a brief interpretation of the results in some cases
Date: July 1960
Creator: Batch, M. L. & Snidow, N. L.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Hot Exponential Experiment

Description: A series of exponential experiments were performed using Consolidated Edison Thorium Reactor oxide type fuel pins in a light water lattice. These experiments were performed in a new facility where measurements were made at temperatures up to 468 F. In addition, boric acid was added to the system in various concentrations. The main objective of these experiments was to obtain the change in material buckling for the system as operating conditions were changed from ambient temperature to high t… more
Date: June 1960
Creator: Clark, R. H.; Barrett, L. G. & Funderburg, J. M.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor: Reactor Vessel Internal Components Design

Description: The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods.
Date: July 1960
Creator: Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
Partner: UNT Libraries Government Documents Department
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Control Blade Worth by Partial Water Height and Soluble Boron Methods

Description: The series of experiments described in this paper was performed to determine reactivity values of various patterns of fully inserted cruciform control blades. The experiments yielded the worth of fully inserted blade patterns in terms of their holddown characteristics.
Date: July 1960
Creator: MacKinney, Arland L. & Ball, Russell M.
Partner: UNT Libraries Government Documents Department
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Corrosion Product Activity Distribution Across the Chemical Process System in the Consolidated Edison Thorium Reactor Plant

Description: A study has been performed to determine the corrosion product and water impurity activities in the CETR Chemical Process System. A simplified mathematical model is used to represent the physical situation; however, the magnitude of the activities, taken at the end of the core life to represent the most conservative case, is considered sufficiently accurate for engineering calculations.
Date: August 1960
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Design of the Movable and Fixed Control Components for the Consolidated Edison Thorium Reactor

Description: Prototype testing and thorough design analyses have proven the control components for the Consolidated Edison Thorium Reactor are adequate to withstand loads imposed during operation and handling. Assumptions made in the design analyses and cycles run during prototype testing subjected the components to more rigid conditions that are anticipated during actual operation. Results indicate the control components meet their design requirements.
Date: August 1960
Creator: Gestson, D. K.; Collings, D. M. & Maynard, W.
Partner: UNT Libraries Government Documents Department
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Development and Testing of Low Cost Fuel Elements for Power Reactor Service

Description: The development of swaging and vibratory compaction process for fabrication of clad UO2 fuel rods is described. The cost is less than 50% of that for an equivalent core fabricated from pellets. The irradiation testing of vibratory filled and swaged UO2 rods is reported for burn-ups from 2,000 to 12,000 Mwd/t UO2; the results indicate that the rods are capable of excellent performance power reactors.
Date: June 2, 1961
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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The Effects of Fuel Rod Fission Product Leakage on the Consolidated Edison Thorium Reactor Plant

Description: Experiments performed by WAPD and others have shown that with fuel in an oxide form, it is possible to continue to operate a nuclear plant with fuel rods that have developed defects with only a small increase in the radiation contamination problem
Date: June 1960
Creator: Montgomery, D. W.; Howard, J. O. & Dodd, R. H.
Partner: UNT Libraries Government Documents Department
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Fuel Element Structural Design and Manufacture for the Consolidated Edison Thorium Reactor Plant

Description: The design of the fuel-element structure for the CETR is described. Component parts of the assembly comprise the fuel-bundle assembly, the fuel-can assembly, the upper transition, the fuel-element spring, and the upper nozzle and seal assembly.
Date: September 1960
Creator: Collings, D. M.; Gestson, D. K.; Andrea, C.; Ferris, H. D.; Boyer, R. L. (Ralph L.), 1910- & Larson, G. C.
Partner: UNT Libraries Government Documents Department
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Geometric and Temperature Effects in Thorium Resonance Capture for the Consolidated Edison Thorium Reactor

Description: Although there have been several previous investigations of neutron resonance absorption in thorium, knowledge in this area has not been sufficiently accurate nor extensive enough to satisfy the practical requirements of thorium breeder reactor design. The present experiment was performed in an effort to reduce this uncertainty by checking and extending the results of previous measurements of the geometric and temperature dependence of thorium resonance integrals. The experimental procedure w… more
Date: June 1960
Creator: Pettus, W. G.
Partner: UNT Libraries Government Documents Department
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Graphite-to-Metal Seal Screening Tests

Description: In the basic design for a two-fluid LMFRE, a seal has to be made between the metal core inlet and the graphite bottom reflector. To evaluate the effectiveness of such a method of sealing, a screening test apparatus was constructed to determine quickly the physical parameters and the best configuration for interface contact
Date: September 1958
Creator: Gilhart, J. S.
Partner: UNT Libraries Government Documents Department
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Irradiation Performance of Thoria-Urania Fuel Materials: Quarterly Technical Report, Number 2, October - December 1964

Description: From introduction: "Complete exploitation of the advantages of thorium as a fertile material in thermal and particular resonant spectrum reactors has been inhibited by the lack of quantitative physical property data for thoria and thoria-urania fuels."
Date: October 1964
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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Irradiation Test Program for the Consolidated Edison Thorium Reactor

Description: The Irradiation Test Program for the Consolidated Edison Thorium Reactor was conducted to obtain confirmation of the stability and performance of the reference fuel element materials and of test assemblies under design operation conditions. The irradiated specimens were tested to determine mechanical properties and corrosion resistance to borated water.
Date: August 1960
Creator: Baker, P. B.; Dzura, E. J. & Johnson, C. R.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment, Cavitation by Bismuth

Description: From abstract: "Croloy 2 - 1/4 was tested to determine the causes and effects of cavitation in dynamic liquid bismuth solutions."
Date: December 1959
Creator: Hovanec, F. L.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop

Description: This report provides an overview of the creation of the Liquid Metal Fuel Reactor Experiment program. It furthers the work by constructing a single loop to test all the components required for the 16 loop reactor. This utility loop was also constructed to provide a facility for testing various components such as valves and flow meters.
Date: May 5, 1959
Creator: Baker, O. H.
Partner: UNT Libraries Government Documents Department
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