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AbstractAbstract
[en] This report details the many facets of analysis, design and operation which, taken together with the great co-operative efforts of a large number of the operating and engineering staff of the Dragon Project, records the events in a major refit to the core region of the High Temperature Reactor Experiment (Dragon). (author)
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30 Jan 2023; 234 p; Country of input: International Atomic Energy Agency (IAEA); Document from Juelich Preservation Project; Refs., figs., tabs.
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[en] This report describes the design of the two forms of Dummy Fuel Element used in the Dragon Reactor. The limitations of the designs are discussed and it is shown that for their projected use no serious operational restrictions exist. It is, however, concluded that dummy elements should not be left in the core during full temperature or power operation of the reactor. (author)
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Jun 1964; 34 p; Country of input: International Atomic Energy Agency (IAEA); Document from Juelich Preservation Project; 9 refs., 2 figs.
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[en] In this report four designs of prismatic fuel pin suitable for use in HTR power reactors are described and their relative thermal performance in a fully and continuously gagged core with a gas outlet temperature of 800°C is compared. The stresses arising in fuel pins are described and the nature of the change in these stresses during irradiation is discussed. Attention is drawn to the importance of the material properties and their variation with irradiation dose and particularly to the need for defining the properties of the fuel matrix. (author)
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May 1970; 25 p; Country of input: International Atomic Energy Agency (IAEA); Document from Juelich Preservation Project; 12 figs., 2 tabs.
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AbstractAbstract
[en] Consolidation of polychlorinated biphenyl (PCB) wastes is recommended for improving ownership control of wastes, eliminating PCB storage sites, and increasing cost-effectiveness of waste management. In Ontario, sites receiving the waste must be owned by the waste generator and registered as a PCB site. All PCBs must be removed from a site with no contaminated materials or wastes left behind, which requires a thorough site assessment to identify wastes prior to removal, a sampling and analytical scheme if necessary, and an approved plan for site cleanup. If large volumes of PCB-contaminated oil are involved, it may be cost-effective to put oil from several sites into bulk tanks and thus avoid the need to handle and decontaminate a large number of drums. With low volumes of oil, it may be possible to move the waste to another site where mobile PCB destruction is taking place. It also may be possible to get approval to blend high-level PCB liquids with mineral oil to reduce the PCB concentration to a level where chemical decontamination is allowed. For large volumes of high-level PCB wastes, consolidation will be necessary simply because of the high costs of mobilizing an incinerator and the requirement for public hearings for each incineration project. To make such a project cost-effective, PCB wastes will have to be concentrated from a large geographic area. 1 fig
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Journal Article
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AbstractAbstract
[en] In this report four designs of prismatic fuel pin suitable for use in H.T.R, power reactors are described and their relative thermal performance in a fully and continuously gagged core with a gas outlet temperature of 800°C is compared. The stresses arising in fuel pins are described and the nature of the change in these stresses during irradiation is discussed. Attention is drawn to the importance of the material properties and their variation with irradiation dose and particularly to the need for defining the properties of the fuel matrix. (author)
Primary Subject
Source
Oct 1969; 28 p; Country of input: International Atomic Energy Agency (IAEA); Document from Juelich Preservation Project; 15 figs., 2 tabs.
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AbstractAbstract
[en] This report gives a brief description of the design and manufacture of the Thermal Column of the Dragon Reactor. (author)
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Source
Apr 1964; 10 p; Country of input: International Atomic Energy Agency (IAEA); Document from Juelich Preservation Project; 4 refs., 3 figs.
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AbstractAbstract
[en] The final design of fuel element for first core loading in the Dragon Reactor is described and its operational characteristics are discussed. This report does not describe the manufacture of the fuel cartridges nor does it discuss the efficiency of the purge system. The expected temperature distribution in the fuel rod assemblies is presented graphically and thermal strains arising therefrom are evaluated. The effects of irradiation induced dimensional changes are considered and it is shown that in the absence of creep this is the most important structural and material factor in limiting the life of an element in the core. It is further shown that irradiation induced creep can significantly alter the distribution of such strains in a fuel tube in a very short time, and that complete relaxation of thermal strains may occur. If creep occurs then the maximum stress evaluated from existing data, which will occur in a cold tube with the reactor shutdown, is shown to be safe if a maximum surface temperature of 1030° is not exceeded during operation at full power. With regard to pressure excursions, from whatever cause, no serious limitations exist. (author)
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Jul 1965; 60 p; Country of input: International Atomic Energy Agency (IAEA); Document from Juelich Preservation Project; 16 figs., 7 tabs.
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Report
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DEVELOPED COUNTRIES, ENERGY SOURCES, EUROPE, FUEL ELEMENTS, FUELS, GAS COOLED REACTORS, GERMAN FR ORGANIZATIONS, GRAPHITE MODERATED REACTORS, MATERIALS, MECHANICAL PROPERTIES, NATIONAL ORGANIZATIONS, OPERATION, REACTOR COMPONENTS, REACTOR LIFE CYCLE, REACTOR MATERIALS, REACTORS, SHUTDOWN, WESTERN EUROPE
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[en] Precision measurements of the structure of nucleons and nuclei in the regime of strong interaction QCD are now possible with the availability of high current polarized electron beams, polarized targets, and recoil polarimeters, in conjunction with modern spectrometers and detector instrumentation. The authors present some recent results from the Jefferson Lab on the charge and current distributions of nucleons and nuclei. They also review measurements which relate physics at small distances to the regime where strong interaction QCD is the relevant theory
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1 Feb 2000; 567 Kilobytes; International Conference on Quark Nuclear Physics; Adelaide (Australia); 21-25 Feb 2000; JLAB-PHY--00-04; AC05-84ER40150; Available from PURL: https://www.osti.gov/servlets/purl/754539-zs6emX/webviewable/; This record replaces 31026536
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[en] This report gives a brief description of the fuel element design proposed for the first charge of the Dragon Reactor Experiment.
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Jan 1963; 18 p; Dragon Project Fuel Element Symposium; Bournemouth (United Kingdom); 28-29 Jan 1963; Country of input: International Atomic Energy Agency (IAEA); Document from Juelich Preservation Project; 8 refs., 4 figs.
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AbstractAbstract
[en] The Dragon Plant Record is intended to give a detailed account of the design, manufacture, erection, testing and commissioning of all main reactor components and to act as a guide to internal Dragon documents containing more detailed information for each particular plant, nach major part is identified by its Plant Identity Number. Many of the documents referred to are not available for general distribution. Any requests for further information should be addressed to The Chief Executive, O.E.C.D. High Temperature Reactor Project (Dragon), AEE, Winfrith, Dorchester, Dorset, England. (author)
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Mar 1965; 23 p; Country of input: International Atomic Energy Agency (IAEA); Document from Juelich Preservation Project
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