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Revisions to Experimental Gas Cooled Reactor, Final Hazards Summary Report: Volume 2, Plant Operation

Description: From introduction: This report is a revision to a previous edition: The information provided in Volume II describes programs, requirements, and procedures established by the Operator to minimize the probability of equipment failure, actions taken during any emergency to minimize radiation exposure dose to the general public and to plant personnel, and actions taken following a hazardous condition to prevent its recurrence.
Date: July 1965
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Gas Cooled Reactor, Final Hazards Summary Report: Volume 2, Plant Operation

Description: From introduction: The information provided in Volume II describes programs, requirements, and procedures established by the Operator to minimize the probability of equipment failure, actions taken during any emergency to minimize radiation exposure dose to the general public and to plant personnel, and actions taken following a hazardous condition to prevent its recurrence.
Date: August 1, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Rotating Machinery for Gas-Cooled Reactor Application

Description: From foreword: Representatives from various organizations met to discuss progress in the development of rotating machinery for gas-cooled reactors. The equipment covered included main blowers, shaft seals, gas turbines, gas bearing compressors, and other types of special compressors for reactor or experimental applications.
Date: June 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transient Reactor Aerothermodynamics

Description: The transient aerothermodynamic processes in a gas-cooled reactor are described in a simplified manner to illustrate some of the fundamental physical phenomena involved, to provide some approximate but useful methods of analysis, and to aid in the understanding and use of more complex computer solutions. The transient heat balance equation for an element of a single reactor channel is derived in terms of aerothermodynamic time constants, and typical analytic solutions for transients are presented. This equation is used in generating the time-dependent equation for the channel exhaust gas temperature. The single-channel analysis is extended to multiple channels. A method for determining the approximate transient temperature envelopes for various reactor components is presented. The effects of aerodynamic and thermal coupling between different reactor channels are illustrated. Some of the simplifying assumptions are investigated with respect to the conditions under which they are valid.
Date: November 18, 1963
Creator: Rodean, Howard C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development, Research and Development Programs Quarterly Progress Report: April - June 1964

Description: The programs sponsored by the Division of Reactor Development at Hanford include studies on basic properties of fuel materials and fabrication methods, physics, chemical processing of reactor fuels and radioactive waste, material development, irradiation effects on materials, fuel cycle analysis and advanced concepts, instrumentation, and nondestructive testing techniques. The results of these programs are broadly applicable to the Civilian Application Program.
Date: November 1964
Creator: Pacific Northwest Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fission-Product Release from UO2

Description: Release of fission products from UO2 with emphasis on fuel elements operated at higher surface temperatures and lower external pressures than those for pressurized-water systems.
Date: September 13, 1960
Creator: Cottrell, W. B.; Culver, H. N.; Scott, J. L. & Yarosh, M. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas Cooled Nuclear Reactor Study

Description: Study of a gas cooled reactor with design specifications providing for a source of high temperature heat to a stream of helium. This reactor, in turn, is used as a source of heat for the air stream in a gas-turbine power plant.
Date: July 31, 1956
Creator: Thompson, A. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison of Optimum Natural Uranium Nuclear Power Plant and Optimum Enriched Uranium Nuclear Power Plant

Description: Report that "compares the designs of an optimum natural uranium power plant and an optimum partially enriched uranium power plant, both using CO2 as a coolant" (p. 1). Includes a description of each plant's design, construction, and economic considerations.
Date: August 1958
Creator: Kaiser Engineers
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Appendix to Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission Idaho Operations Office Contract No. AT(10-1)-925

Description: Report containing outlines of operating procedures, costs, construction, safety analysis, studies, and design specifications of a 30,000 kilowatt prototype partially enriched uranium nuclear power plant.
Date: March 1959
Creator: Kaiser Engineers
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of Fueled Graphite Containing Pyrolytic-Carbon Coated Carbide Particles for Nonpurged, Gas-Cooled Reactor Systems

Description: Abstract: Progress is reported in several areas of development of fueled graphite containing coated particles for nonurged gas-cooled reactor systems. The sol-gel process has been modified for making spherical particles of both thorium-uranium carbide and thorium-uranium oxide suitable for coating. Equipment has been assembled and methods have been developed for deposition of pyrolytic-carbon coating under well-controlled conditions. Damage to coated particles during fabrication into a graphite matrix depends on the molding pressure and the volumetric content of coated particles. Vendor-supplied coated particles and fueled graphite spheres have been evaluated extensively in both in- and out-of-reactor tests. Duplex- and triplex-coasted particles have excellent fission-gas retention at 2050 degree F to burnups of 15 at. % burnup. Fueled graphite spheres containing coated particles have good irradiation performance, but the fission-gas release rates are somewhat higher than for unsupported coated particles. Fueled graphite spheres react with water vapor about as rapidly as do Speer Mod-2 and ATJ grades of graphite. The diffusion rates in pyrolytic carbon are the same for uranium, thorium, and protactinium. The diffusion rates in the direction parallel to the deposition plane are much higher than those in the perpendicular direction.
Date: November 1963
Creator: Carlsen, F. L., Jr.; Bomar, E. S. & Harms, W. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of the Helium-Argon System

Description: A semi-empirical relation for the thermal conductivity of helium-argon gas mixtures is suggested. The analyses used in support of the proposed conductivity relations are based on low-temperature (T < 800 degrees C) thermal conductivity data for helium, argon and helium-argon mixtures. The report is a compilation of available data and theories, and does not contain any new experimental results. With the approach presented here, one should be able to predict thermal conductivities of helium-argon mixtures to within 5% of their true values for temperatures up to 1200 K. The recommended equations are best estimates and should be treated as such. A definite need exists for experimental data to verify or modify the recommendation.
Date: February 1979
Creator: Purohit, A. & Moszynski, Jerzy R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transient Thermal Stress in Tubular Reactor Elements

Description: In this paper, a theoretical solution is developed for the transient thermal stress distribution in a reactor fuel tube of circular cross sections with spatially uniform internal power generation and forced convective heat transfer at the inner surface of the tube. Solution of the equation of heat conduction is done my means of a Laplace transform with subsequent application of the inversion integral to arrive at a final expression for the transient temperature distribution. The solution is of interest in the analysis of transients in reactors which use either a gas or liquid heat transfer medium. The work was initiated in conjunction with the quench testing of ceramic fuel elements for a gas-cooled reactor. Expressions for the component stresses are given explicitly and examples of application of these formulas to startup of a gas cooled reactor and the flow quenching of a fuel tube are given.
Date: September 1960
Creator: Deverall, LaMar Ivan
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Study of the Variables Affecting the Corrosion of Beryllium in Carbon Dioxide

Description: Beryllium is a favoured canning and/or moderating material in the proposed Australian High Temperature Gas Cooled Reactor. With carbon dioxide as the most likely coolant a detailed knowledge of the corrosion of beryllium in this gas is required. Two separate investigations have proceeded simultaneously. First the effect of the following variables was studied; surface preparation of the specimen, temperature (100—725ºC), pressure (0—280 p.s.i.g.), velocity, and impurity content of the gas. The influence of irradiation has not yet been studied. Autoclaves, thermobalances, and dynamic loops were used. The results were statistically analysed and kinetic data obtained. In all cases specimens with etched surfaces yielded approximately 25 — 30 per cent, greater weight gains than specimens with ground or polished surfaces. On extruded material no "breakaway" oxidation was encountered below 650ºC in commercially dry gas (< 20 p.p.m. moisture). The rate of attack was to some extent affected by the pressure of the gas. Breakaway was only observed in one series of specimens at 650ºC. In this particular case the gas pressure was 280 p.s.i.g. However, it seems that surface temperatures of beryllium cans made from extruded material should be maintained below 650ºC in a reactor system using the commercially pure carbon dioxide as coolant. In the second approach a more basic study of the chemistry of the reaction was made as well as a detailed investigation into the variation caused by differences in the composition and fabrication of the metal. Spiral spring balances at atmospheric pressure were used. Extruded material made from beryllium powder oxidized in dry oxygen for a short period of time had greatly enhanced oxidation resistance when exposed to carbon dioxide. Some of the material exposed to wet carbon dioxide at 700ºC and atmospheric pressure did not exhibit "breakaway" oxidation. The weight gains after 1,000 hours exposure under …
Date: December 1961
Creator: Draycott, A.; Nicholson, F. D.; Price, G. H. & Stuart, W. I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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