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SRE CONTROL ROD SHIELDING REQUIREMENTS

Description: Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended pow… more
Date: October 22, 1957
Creator: Whittum, H.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

20,000 KW Nuclear Power Plant Study for United States Atomic Energy Commission

Description: Introduction: In September of 156, Gilbert Associates, Inc., entered into a contract with the United States of America, acting through the United States Atomic Energy Commission, for the study and preliminary design of a nuclear power plant being considered for integration into a central station power system at an overseas site.
Date: July 7, 1957
Creator: Gilbert Associates, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Single-Fluid Two-Region Aqueous Homogeneous Reactor Power Plant Conceptual Design and Feasibility Study. Final Report

Description: The feasibility of a 150 Mwe aqueous homogeneous nuclear power plant was investigated by a joint study team of the Nuclear Power Group and The Babcock & Wilcox Company. In this concept, the reactor is a single-fluid two-region design in which the fuel solution circulates through the thoria pellet blanket as the coolant. Componeats and plant arrangement were designed to provide maximum overhead accessibility for maintenance. All components in contact with reactor fuel at high pressure are themse… more
Date: July 1, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hazard Summary Report on the Argonne Low Power Reactor (ALPR)

Description: The over-all design of the Argonne Low Power Reactor is presented. Detailed design data are given as well as information concerning the hydrology, seismology, and meteorology of the building site (NRTS). In addition, a description of the reactor instrumentation and control, mechanical design, heat transfer, and related physics are presented. A full description of the power plant, including the steam and electrical systems, is also given, as well as the operating procedure for both normal and em… more
Date: October 1, 1957
Creator: Smaardyk, A. ed.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Calder Hall Type of Nuclear Power Plant

Description: Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.
Date: January 18, 1957
Creator: Banks, William F.; Schneider, G. A.; Morgan, William T. & Ash, E. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Hydraulic Power Unit for Solvent Extraction Column Pulse Generators

Description: A power unit comprised of a reciprocating hydraulic cylinder controlled by hydraulic, mechanical, and electrical elements was developed to drive pulse generators for solvent extraction columns in the Purex Hot Semiworks. Design bases included remote control of continuouslyvariable pulse amplitudes between 1/ 2 and 1/2 inches, and pulse frequency up to 120 cycles/min. Each of nine power units operated 30 to 60 million cycles without serious difficulty, although minor modifications and correction… more
Date: August 23, 1957
Creator: Kelly, V. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast-Period Reactor Safety Fuse Tests

Description: The combination of an effective fuse with a sensitive trigger is investigated. Tests conducted with two types of fuse, the annular-passage and the control-rod-type fuse, are described and analyzed. Appendixes present the methods of analysis and calculation, an analysis of fuse performance, and a summary of alternative fuse trigger and fuse system designs, with methods for adaption of fuses to power reactors. (auth)
Date: June 1, 1957
Creator: Stilwell, S.N. & Waterfield, R.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Pressurized Water Reactor Program Technical Progress Report for the Period July 15, 1954 to August 26, 1954

Description: This progress report has 2 parts. Part 1 PWR Engineering covers the following topics: (1) power plant analysis and systems; (2) power plant components and component materials and tests; and (3) reactor and auxiliaries. Part 2 PWR Development covers: (1) fuel element development; (2) metallurgy of core materials; (3) materials application development; (4) chemistry development; (5) irradiation effects; and (6) reactor physics.
Date: October 31, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE DEVELOPMENT OF COMPOSITE CONTROL RODS FOR WATER-COOLED POWER REACTORS

Description: The phrase "composite control rod" is used to describe a hafnium-tipped titanium-boron control component with a titanium cladding. Blades for such cortrol rods were successfully prepared in cooperation with the Battelle Memorial Institute by a picture-frame rolling technique. The rolling packs, which are machined from type 304 stainless steel, contain slntered titanium boron and wrought hafnium core materials in a commercially pure titanium envelope. Such packs are evacuated, sealod off, and ro… more
Date: October 15, 1957
Creator: Ray, W.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PRELIMINARY HAZARDS SUMMARY REPORT. PART B. LICENSE APPLICATION

Description: The proposed Yankee Atomic Electric Company Reactor is a pressurized light water reactor plant designed to produce ultimate1y 492 Mw of heat and 134 Mw of net electrical generation at full power. The initial core to be operated in the reactor is designed to produce 392 Mw of heat at full power which provides approximately 110 Mw of net electrical generation. The reactor is fueled with slightly enriched uranium dioxide UO/sub 2/, in the form of pressed and sintered 0.3 in. diameter cylindrical c… more
Date: April 1, 1957
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

AN EVALUATION OF HEAVY WATER REACTORS FOR POWER

Description: Reference designs for pressurized and direct-boiling D/sub 2/O reactors were prepared for electrical outputs of 20, 100, and 250 electrical Mw. A number of possible core designs were considered and those utilized which seemed most appropriate to give low-cost power. The technology and costs available today were employed in the preparation of the over-all plant designs. The Consolidated Western Steel Division of U. S. Steel Corporation assisted by preparing a comprehensive report on the design o… more
Date: October 1, 1957
Creator: Herron, D.P.; Newkirk, W.H. & Puishes, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SUPERHEATING WATER-BOILER. Reactor Design and Feasibility Study

Description: A preliminary design is presented for a boilingwater reactor with integral nuclear superheater, which produces steam at 1200 psia, 950 deg F. The design uses stainless steel, UO/sub 2/, and water for materials and stays generally withln the limits of existing reactor technology. The design output is 129,445 lbs of steam per hour at the stated conditions, which corresponds to 17,500 shaft horsepower in a naval steam plant and to 47.25 Mw of heat. This is thought of as a ship propulsion reactor, … more
Date: August 1, 1957
Creator: Marbury, F.; Alden, J.W.; Bedford, R.E.; Bilenas, J.A.; Coppersmith, W.C.; DeVincentis, J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Critical-Assembly Experiments on a Reflector Control System for a Boiling Reactor

Description: Research directed toward an evaluation of a reflector control scheme for a small boiling heterogeneous reactor is reported. The control method uses the ambient reactor steam pressure to adjust the height of a radial water reflector. Critical-assembly experiments were conducted to measure the reflector worth and the effect of nonhomogeneous voids. The critical-assembly core approximated a right circular cylinder 24 in. high and 21 in. in diameter. The core was made up of polyethylene strips to s… more
Date: December 20, 1957
Creator: Dingee, David A.; Hogan, William S.; Wilson, Robert G.; Ballowe, William C.; Jankowski, Francis J. & Chastain, Joel W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Study of Core Fuel Systems for a Fast Breeder Power Reactor

Description: The first phase of a program aimed toward the development of materials and a core-subassembly design for the second core of the Fermi Reactor is outlined. The ground rules established by APDA for the study were based upon the performance requirements of the reactor plant with some modification to permit hlgher power generation and upon a value of Pu produced of about per g. Consideratlons of various factors led to the selection of the dispersion or cermet fuel as havlng the most potential for t… more
Date: November 1, 1957
Creator: Fawcett, S.L. ed.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

GAS COOLED PEBBLE BED REACTOR FOR A LARGE CENTRAL STATION. Reactor Design and Feasibility Study

Description: An optimum econonic design for a high temperature, helium cooled, central station reactor power plant of about 400 Mw of electric power was determined. The core consists of a randomly packed bed of unclad graphite spheres, approximately one in. in diameter, impregnated with U/sup 233/ and thorium such that a conversion ratio of near unity is achieved. The high temperature helium permits steam conditions, at the turbine throttle, of 1000 deg F and 1450 psia. (auth)
Date: August 1, 1957
Creator: Schock, A.; Bruley, D.F.; Culver, H.N.; Ianni, P.W.; Kaufman, W.F.; Schmidt, R.A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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