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Studies of Reactor Containment : Monthly Technical Progress Report No. 32

Description: The report covers work performed during the period December 1, 1959 through December 31, 1959. The general objectives of the program of "Studies of Reactor Containment" are to accomplish theoretical and experimental investigations of the loads to which external containment structures for nuclear reactors are subjected in the vent of a violent incident at the reactor core, the evaluation of methods of reducing that loading, and the study of the response of and design criteria for external contai… more
Date: January 15, 1960
Creator: Zaker, T. A. (Thomas Allen)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Studies of Reactor Containment : Combined Monthly Technical Progress and Financial Status Report No. 20

Description: This combined Progress and Financial Status Report cover work performed during the period December 1, 1958 through December 31, 1958, and summarized the financial status of the progress as of December 1, 1958. The objectives of the program of "Studies of Reactor Containment" are to accomplish theoretical and experimental investigations of the loads to which external containment structures for nuclear reactors are subjected in the vent of a violent incident at the reactor core, the evaluation o… more
Date: January 19, 1959
Creator: Zaker, T. A. (Thomas Allen)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Note on the Kinetics of Homogeneous Piles

Description: Abstract. In investigating stability of a homogeneous pile it has been customary to assume that the production of bubbles follows the production of power instantaneously. Here we investigate the implications of introduction of an intermediate dissolved gas stage under two hypotheses on the formation of bubbles from this dissolved gas. It is seen that this additional stage tends to make the pile unstable.
Date: June 26, 1945
Creator: Wilkins, J. Ernest, Jr., 1923-2011
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report June - September 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of covering the complete reactor neutron flux start range from 10(3) - 5 x 10(13) nv by using in-core chambers. The counting mode of operating will be used at low neutron fluxes and the root mean square voltage fluctuation mode will be used at high neutron flux levels. Experiments have been run utilizing various ion chambers, gases, gas pressures, voltage, and cables to measure sensitivities and range operating … more
Date: October 1963
Creator: DuBridge, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Doppler and related measurements in a soft fast-reactor spectrum

Description: This report deals with a group of both theoretical and experimental investigations which have been carried out, utilizing Core 15, one in a series of critical assemblies that have been constructed at Atomics International's Epithermal Critical Experiments Laboratory (ECEL).
Date: March 24, 1969
Creator: Springer, T. H.; Tuttle, R. J.; Otter, J. M. & Pachall, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Large High Power Density Core - Interim Report I: Physics Description of Reference Design

Description: A reference design of a large high power density core has been established representing the available technology as of August, 1960. Reference core performance and cost should improve considerably after incorporation of improvements now under study.
Date: February 3, 1961
Creator: Miller, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report September - December 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. The counting mode of operation will be used at low neutron flux levels and the RMS voltage fluctuation mode (Campbell Theorem) will be used at high neutron flux levels. The June-September Progress Report (GEAP-4386) shows how the RMS voltage mode can be used, discusses c… more
Date: January 1964
Creator: DuBridge, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report January - March 1964

Description: The objective of Project Agreement 22 is to determine the feasibility of using in-core ion chambers to cover the complete reactor neutron flux startup range from 10(4) -5 - 10(13) nv using in-core ion chambers. This technical report discusses the following topics: low versus high cable termination impedance, amplifier considerations, noise considerations, gas and pressure selection, cable selection, effect of gamma, effect of temperature, and remaining problems.
Date: April 1964
Creator: DuBridge, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility Report on Fast Exponential Experiment

Description: The general program established at Argonne National Laboratory in connection with the Fast Power Breeder Reactor (PBR) includes performance of exponential experiments on assemblies having compositions which may exist in the reactor core. This report deals with that phase of the program known as the Fast Exponential Experiment which may be described very briefly as follows. An assembly of fissile (U-235) and fertile material (too small to be self-critical) intermixed with poisons (such as are en… more
Date: June 10, 1953
Creator: Brittan, R. O.; Hummel H. H.; Livingood, John J. (John Jacob), 1903-; Martens, F. H. & Spinrad, Bernard I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Multiplication of Enriched Loading in Exponential Pile

Description: This report refutes earlier calculations made in the flux level of exponential piles. The results of the earlier calculations made on subcritical assemblies using critical assembly equations are in error. The calculations used in this report were more successful.
Date: September 28, 1953
Creator: Farrand, W. B. & Lloyd, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Lynchburg Test Reactor: Critical Experiment, Hazard Evaluation

Description: This report summarizes the hazards associated with the operation of the Lynchburg Test Reactor (LTR) critical experiments. The LTR critical experiment program is outlined and the design of the experiment is described. The experiments will provide basic data to check two-dimensional calculational methods and provide information needed in the design of the LTR.
Date: November 1959
Creator: Engelder, T. C. & Schutt, P. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor: Determination of the Purification Rate for Normal Operation

Description: The objective of this study is to establish a primary loop purification rate for normal operation to (1) maintain the activity created in the primary coolant water by corrosion products and other impurities (excluding fission products) at tolerable level and (2) minimize the crud deposition on the core heat-transfer surfaces.
Date: June 1958
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor Project: Technical Progress Report for the Period April 1, 1957-October 1, 1957

Description: Quarterly report on the development of a nuclear reactor for merchant ships. Included in this report are costs on testing and development of a core reactor, design and manufacturing techniques, and other elements required for a successful reactor design and functionality.
Date: 1957
Creator: The Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Merchant Ship Reactor Project: Technical Progress Report for the Period October 1957-December 1957

Description: Quarterly report on the development of a nuclear reactor for merchant ships. This report covers details of a modified propulsion system, completing the basic design of reactor auxiliary systems, control rod effectiveness, and other continued design elements.
Date: 1958
Creator: The Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Burst Characteristics Associated with the Slow Assembly of Fissionable Materials

Description: This technical report is a sequel to LA-596, "Efficiency for Very Slow Assembly" by K. Fuchs. Herein are given estimates of temperature rise and pressure developed as a result of active material slowly being driven supercritical. Marginal assembly rates can thus be determined for both metal and solution assemblies above which the disassembly by thermal expansion is explosive in the sense that the active material or containing vessel is ruptured.
Date: July 1952
Creator: Hansen, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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