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GCRE-I HAZARD SUMMARY REPORT

Description: The GCRE-I hazard summary report is supplemented in the following areas: geometry and operation of the steam cooling system, the reactor coolant by-pass, and by-pass valving; the means by which by-passed circuits are prevented from remaining unintentionally disabled; design details, and details of procedure for core flooding operations. (A.C.)
Date: March 1, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Final Report

Description: >The basic fuel element consisted of a uniform dispersion of fuel in a 1 1/2 inch diameter graphite sphere. Ceramic coatings for the retention of fission products were studied. It was found-that molecularly deposited'' ceramics such as alumina, siliconized silicon carbide, and pyrolytic carbon were excellent barriers to fission product leakage. The most advantageous location for ceramic coatings was found to be on the individual fuel particles, where the coating was subject to smaller forces an… more
Date: April 30, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Supplementary Study. Extrapolation to Large Central Station Integral Nuclear Superheat Plant

Description: An evaluation was made of the maximum size plant for which the BONUS reactor plant could serve as a realistic prototype and the design changes required to increase the size and characteristics for the present BONUS design such that it could serve as a realistic prototype for the largest feasible integral-superheat reactor power plant. (M.C.G.)
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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New Hot Laboratory Facilities at Los Alamos

Description: New Hot Laboratory Facilities which support three major research programs directed by the Los Alamos Scientific Laboratory of the University of California are described. For the Nuclear Rocket Propulsion Program, a hot cell addition to the Radio Chemistry Building at Los Alamos will be completed early in 1963, and construction is expected to start soon on the hot cell addition to the Maintenance, Assembly and Disassembly Building at the Nuclear Rocket Development Station in Nevada. Integral hot… more
Date: January 1, 1962
Creator: Wherritt, Charles R.; Franke, Paul R.; Field, R. E. & Lyle, A. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A Mechanism Explaining the Instability of EBR-I, Mark III

Description: Presented at the International Atomic Energy Agencysponsored Seminar on the Physics of Fast and Intermediate Reactors. Vienna, August 3-11, 196l. A feedback model, was developed to account for resonant instabilities in the Mark II core. In this model, the prompt positive power coefficient effect is ascribed to fuel rod bowing and the delayed negative power coefficient effect to thermally lnduced motions in the lower shield plate. Since this model is supported by observations, it is concluded th… more
Date: September 1, 1961
Creator: Smith, R. R.; Matlock, R. G.; McGinnis, F. D.; Novick, M. & Thalgott, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Program, a Boiling Water Reactor Research and Development Program. Third Quarterly Report, January 1961-March 1961

Description: The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulat… more
Date: October 31, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY

Description: For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date: January 1, 1960
Creator: Gronemeyer, F.C. & Merryman, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis and Optimization of "Full-Length" Diodes

Description: A method of analyzing the axial variation of the heat generation rate, temperature, voltage, current density and emitter heat flux in a thermionic converter is described. The method is particularly useful for the case of "long" diodes, each extending over the full length of the reactor core. For a given diode geometry and fuel distribution, the analysis combines a nuclear solution of the axial fission density profile with the iterative solution of four differential equations representing the th… more
Date: unknown
Creator: Schock, Alfred
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Management in Large Pressurized Water Reactors

Description: Economic and operational ground rules and their effects on fuel management are summarized, and examples showing the approach to typical fuel management problems are presented. The problems associated with in-core fuel management are also discussed, and the merits of various fuel cycling methods are evaluated. (D.C.W.)
Date: October 31, 1964
Creator: Dollard, W. J. & Strawbridge, L. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Plutonium Recycle in the Calder Hall Type Reactor

Description: The economiics and physics of four schemes of pIutonium recycle in the Calder Hall type reactor are considered. The four possible schemes are: (I) to blend the Pu produced In a run with fresh naturaI U for a subsequeut run; (2) to alloy the Pu with somie diIuent metal and fabricate the alloy Into high heat- transfer elements morc like MIR or PWR-sced type elements and"spike' a subsequent load of fresh natural U elemients with these Pu elemicnts; (3) to recycle half the spent U as well as the Pu… more
Date: January 1, 1958
Creator: Barbieri, L. J.; Webster, J. W. & Chow, K. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Estimates of the Thermal and Hydraulic Performance of Advanced Reactor Cores

Description: The equations used in advanced reactor core calculations and a semigraphical method for their solution are presented. The following fuel elements are analyzed: continuous plates, parallel-flow rods, cross-flow rods, tubular flow channels in a solid matrix of fuel, and pellets. (M.H.R.)
Date: September 20, 1954
Creator: Ewen, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pressure Drop, Flow Distribution and Mixing Studies for a Model Heterogeneous Reactor Vessel

Description: A series of hydrodynamic tests was conducted on a 1: 12 scale mcdel of the Yankee reactor vessel and core with four, three, and two loop operation. There was no depression of flow in the center of the core due tc the control rod shrouds or shroud support plate. With four loops operating, flow distribution tests at the core inlet indicated that for all operating conditions the highest velocities occurred in the center region of the core and were a maximum of 18% higher than the average velocitie… more
Date: December 1, 1959
Creator: Berringer, R. T. & Bishop, A. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
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Reactor Development Quarterly Progress Report. 4000 Program

Description: The status of Experimenial Boiling Water Reactor development is reviewed. Shell testing, control mechanism development, fuel corrosion, and dimensional stability studies, and design consideration to facilitate D/sub 2/O operation are discussed. Fuel plate and subassembly fabrication, corrosion, and radiation damage studies were continued. Reactor water filtration, purification, and induced activity are considered. High-temperaiure operational tests were run on Experimental Breeder Reactor mecha… more
Date: October 31, 1955
Creator: McLain, S. comp.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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REACTOR ENGINEERING DIVISION QUARTERLY REPORT FOR PERIOD JULY 1, 1954 THROUGH SEPTEMBER 30, 1954

Description: Reactor Programs. The design of the Boiling Experimental Reactor is described. The Borax-1 reactor was intentionally destroyed by suddenly adding 4% excess reactivity. Design of the Borax-II reactor is described. It will be used for studies of transient behavior and steadystate operation as a steam producer. A preliminary design configuration has been established in EBR-II employing central, inner, and outer blankets. Fuel geometries including a smaller pin-type element are being investigated. … more
Date: October 15, 1954
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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