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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.
Partner: UNT Libraries Government Documents Department
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The Variation in Maximum Power Density and Maximum Heat Flux of the Core and Blanket Thorium Plates in the Converter Reactor with Irradiation Time

Description: This report describes how to achieve the variation in maximum power density and maximum heat flux of the core and blanket thorium plates in the converter reactor with irradiation time.
Date: June 23, 1952
Creator: Sletten, H. L.
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.
Partner: UNT Libraries Government Documents Department
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Theory of Oscillating Absorber in a Chain Reacting Pile

Description: Abstract. the fluctuation in pile intensity caused by an oscillating point absorber is calculation. It is found that the nature of the response depends on the frequency of the impressed oscillation. If the frequency is high compared to the decay rate of the high harmonics, the response consists of a wave which is propagated away from the oscillator. If the frequency is low, the propagated wave character of the response disappears and the intensity of the whole pile tends to oscillate with the s… more
Date: April 6, 1945
Creator: Cahn, Albert S., Jr.; Monk, A. T. & Weinberg, Alvin Martin, 1915-2006
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report: Babcock & Wilcox Test Reactor

Description: This preliminary Hazards Summary Report presents to the Atomic Energy Commission (AEC), Division of Licensing and Regulation, a description of the Nuclear Development Center, the characteristics of the proposed site, and an evaluation of the potential hazards associated with operating the test reactor at this location.
Date: July 1962
Creator: Babcock & Wilcox Company
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
Partner: UNT Libraries Government Documents Department
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Flux Distributions and Critical k [infinity] Values for Cylindrical Reactors Simulation the MTR

Description: From summary: "In order to estimate the effect of placing bismuth and thorium layers near the MTR core, radial flux distributions and k[infinity] values were calculated for cylindrical reactors having cylindrical layers of these materials of the same height as the core and beryllium reflector and placed either next to the core or embedded in the beryllium reflector."
Date: June 25, 1952
Creator: Bray, D. T. & McMurry, Henry Lewis, {}
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.
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.
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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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
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
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
Partner: UNT Libraries Government Documents Department
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The Motion of Gas Bubbles in the HRE Reactor Core

Description: This technical report presents "a theoretical study of the motion of gas bubbles in a rotating liquid" in order to "make comparison with experimental data from an investigation concerning the removal of gas bubbles from rotating liquids as descriped in ORNL-630." The report presents a literature review of "motion of gas bubbles in liquids" and provides a "summary of extensive experimental studies at the University of Tennessee." It also presents "an expression for the radial velocity of a gas b… more
Date: January 18, 1952
Creator: Peebles, F. N.
Partner: UNT Libraries Government Documents Department
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Studies of Axial-Leakage Simulations for Homogeneous and Heterogeneous EBR-II Core Configurations

Description: When calculations of flux are done in less than three dimensions, leakage-absorption cross sections are normally used to model leakages (flows) in the dimensions for which the flux is not calculated. Since the neutron flux is axially dependent, the leakages, and hence the leakage-absorption cross sections, are also axially dependent. Therefore, to obtain axial flux profiles (or reaction rates) for individual subassemblies, an XY-geometry calculation delineating each subassembly has to be done a… more
Date: August 1985
Creator: Grimm, K. N. & Meneghetti, D.
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.
Partner: UNT Libraries Government Documents Department
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Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures.

Description: Abstract: Test procedures for special tests involving in-core SM-1 temperature and flow instrumentation are described (Task XIV Package Tests). These tests involve in-core steady state flow and temperature measurements, loss of flow transients, load transients, reduced primary system pressure operations and reduced element flow. The thermal and hydraulic conditions prevailing in these tests, including steady state and transient burnout rations, are developed. The effects of reduced system pres… more
Date: February 28, 1962
Creator: Bradley, P. L. & Coombe, J. R.
Partner: UNT Libraries Government Documents Department
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Hazards Report for the SM-1 Core II With Special Components

Description: Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II and special components. The special components consist of impact specimens, a boron gradient rod, SM-2 elements, a PM-1-M element, and high burnup SM-1 Core I elements. The change in hazards, due to operation of SM-1 with Core II and the special components is evaluated. The analysis indicates there is no change in hazards.
Date: March 30, 1961
Creator: Coombe, J.; Lee, D.; Segalman, I. & Robertson, R.
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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Nuclear Measurements for Type 3 Replacement Cores for SM-1, SM-1A and PM-2A CE 3

Description: Abstract: This technical report contains the description and results of an experimental program to evaluate the effect of utilizing Type 3 (SM-2) replacement cores in existing Army field plants SM-1, SM-1A and PM-2A. This program, conducted at the Alco Products Critical Facility, employed SM-2 mockup fuel elements similar in composition to Type 3 fuel elements to determine start-up characteristics of Type 3 cores in SM-1, SM-1A and PM-2A core configurations. measurements include comprehensive … more
Date: January 11, 1962
Creator: Raby, T. M.; Walthousen, L. D.; Kemp, S. N.; McCool, W. J.; Sontheimer, K. C. & Robinson, R. A.
Partner: UNT Libraries Government Documents Department
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