18,903 Matching Results

Search Results

Advanced search parameters have been applied.

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: The Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department

Evaluation of Coolant Impurity Removal Equipment at the OMRE

Description: Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date: October 15, 1964
Creator: Barbour, P. & Davis, W. W.
Partner: UNT Libraries Government Documents Department

Heat Transfer Characteristics of Graphite Plates with Hydrogen Coolant

Description: "This note presents the results of a parametric study of heat-generating graphite plates with hydrogen coolant flowing through constant area passages. The heat generation within the graphite was assumed to have a distribution that allowed the centerline temperature of the plates to remain constant at 5000 F. The parametric variables were the mass flow rate per unit area, plate thickness, plate length, and passage hydraulic diameter. The machine calculations were coded by Ivan Cherry, T-1."
Date: October 19, 1955
Creator: Bussard, R. W. & Durham, F. P.
Partner: UNT Libraries Government Documents Department

Extended SM-2 Critical Experiments : CE-2

Description: Abstract: This technical report contains a description and results of a second series of critical experiments performed on the SM-2 core mock-up, as additional to the first series of experiments reported in APAE No. 54. The SM-2 core mock-up contains 36.4 kg U-235 and and estimated 67.9 gm B-10. The equivalent diameter and the active height are about 22 in.; the metal-to-water volume ration is 0.344. Data is presented on activation, reactivity, and stuck rod measurements. All measurements were conducted on the open seven control rod array employing 38 stationary fuel elements. Activation measurements consisted of neutron flux measurements using uranium fission foils for relative power distribution studies, the effect of flux suppressors on reducing power peaks, blocked coolant channel measurements, and gamma ray dose distribution. Reactivity measurements were performed to determine the effect f flow divider, flux suppressors and stimulated high temperature and pressure operation; b-10 loading in the SM-2 core; and core material coefficients. For the later, the worth in cents per gm or cents per cc was determined at simulated temperature of 510 degree F for B-10, U-235, stainless steel, and void. Stuck rod measurements were made to obtain an indication of the criticality margin in the event one or more control rods should stick in the operating position.
Date: June 30, 1961
Creator: McCool, W. J.; Robinson, R. A.; Weiss, S. H.; Raby, T. M.; Schrader, E. W. & Walthousen, L. D.
Partner: UNT Libraries Government Documents Department

Transient Flow Performance in a Multi-Loop Nuclear Reactor System

Description: The method present can be used to determine fluid flow and coolant pump speed transients in a nuclear reactor system. Included are transients due to power failure, starting pumps in idle loops, and the opening of an active pump's discharge. Parallel pumps in the system may be analysed independently of each other. Typical cases are presented for the N.S. Savannah (NMSR) and Consolidated Edison Thorium Reactor (CETR).
Date: December 1959
Creator: Boyd, George M., Jr.; Rosser, Ralph M. & Cardwell, Bennett B., Jr.
Partner: UNT Libraries Government Documents Department

Reactor Physics Primer

Description: Report that describes the reactor physics of the processes used to produce plutonium at Hanford Laboratories. This includes a basic explanation of nuclear physics and the principles of the reactor process.
Date: November 15, 1957
Creator: Lockwood, E. H.
Partner: UNT Libraries Government Documents Department

Steam Cooled Power Reactor Evaluation - Beloyarsk (Ural) Reactor

Description: Report evaluating "the effects of nuclear steam superheating, as utilized in the Russian design, on the economics of electric power production, assuming the use of such a design in the United States" (p. 1). This report includes a description of the Beloyarsk Station and modifications made to the Russian designs for use in the United States.
Date: April 1961
Creator: Hanford Works
Partner: UNT Libraries Government Documents Department

Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Description: Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Date: September 1, 1964
Creator: Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
Partner: UNT Libraries Government Documents Department

Practical Reactor Theory

Description: Derivation and basic formulas the physicist or nuclear engineer needs to do the necessary nuclear calculation for a reactor design.
Date: October 21, 1953
Creator: Webster, J. W.
Partner: UNT Libraries Government Documents Department

The H-3 Irradiation Experiment: Irradiation of Experimental Gas Cooled Reactor Graphite, Number 2

Description: Report documenting "the long-term irradiation stability of the graphite used as the moderator in the Experimental Gas Cooled Reactor (EGCR) at Oak Ridge" (p. 1) by irradiating capsules at the General Electric Test Reactor. This includes the design and construction of the experiment, experiment procedures, and results of irradiation. Appendices begin on page 83.
Date: September 1964
Creator: Helm, J. W.
Partner: UNT Libraries Government Documents Department

Neutron-Field and Induced-Activity Measurements-Operation Bren

Description: From Abstract: "Certain characteristics of the neutron field from this unshielded reactor were measured. The activation of gold, manganese, sulfur, cadmium-covered gold, and cadmium-covered manganese was determined as a function of distance from the reactor and of depth in the ground. The data show how those parameters, important for calculating neutron-induced activity in the soil, vary as a function of the height of the source and the slant range from the source."
Date: September 1965
Creator: Tomnovec, F. M. & Ferguson, J. M.
Partner: UNT Libraries Government Documents Department

High Temperature Heat Utilization in Industry

Description: Introduction: The United States Atomic energy Commission has guided the development of nuclear reactors for commercial applications for over a decade. the three most important development areas for industrial applications at the present time are for use in electric power generation, for productions of low temperature process steam, and for the supply of high temperature heat to manufacturing processes.
Date: April 1961
Creator: Ferguson, F. Alan; Towle, Leland H. & Tarrice, Richard R.
Partner: UNT Libraries Government Documents Department

Measurements of thermal distortion of the submarine intermediate reactor "Mark A" moderator tube

Description: Report presenting a moderator tube of the Submarine Intermediate Reactor (SIR) ("Mark A") subjected to temperature gradients considered to be representative of those occurring in the reactor during operation. The distortion of the tube was measured under two conditions: with the ends of the tube retained in the same manner at the reactor and with the ends of the tube simply supported.
Date: December 1952
Creator: Kemp, R. H. & Morgan, W. C.
Partner: UNT Libraries Government Documents Department