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ISBN 13 :
Total Pages : 104 pages
Book Rating : 4.3/5 (91 download)
Download or read book Ultra High Temperature Reactor Critical Experiment (UCX) Safety Analysis Report written by and published by . This book was released on 1965 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Ultra High Temperature Reactor Experiment (Uhtrex) Facility Description and Safety Analysis Report written by and published by . This book was released on 1967 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 376 pages
Book Rating : 4.:/5 (3 download)
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1968 with total page 376 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 54 pages
Book Rating : 4.3/5 (91 download)
Download or read book Quarterly Status Report on Advanced Reactor Technology (ART) for Period Ending ... written by and published by . This book was released on 1965-04-30 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Quarterly Status Report on Ultra High Temperature Reactor Experiment (UHTREX) for Period Ending ... written by and published by . This book was released on 1964-06-20 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book High-temperature Gas-cooled Reactor Safety Studies for the Division of Reactor Safety Research Quarterly Progress Report written by and published by . This book was released on 1979 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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ISBN 13 :
Total Pages : 954 pages
Book Rating : 4.:/5 (2 download)
Download or read book Government-wide Index to Federal Research & Development Reports written by and published by . This book was released on 1965 with total page 954 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : E. E. Burdick
Publisher :
ISBN 13 :
Total Pages : 90 pages
Book Rating : 4.3/5 (91 download)
Download or read book Advanced Test Reactor Critical Facility Safety Analysis Report written by E. E. Burdick and published by . This book was released on 1964 with total page 90 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : U.S. Atomic Energy Commission. Division of Technical Information
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ISBN 13 :
Total Pages : 976 pages
Book Rating : 4.F/5 ( download)
Download or read book Reports Received by Division of Technical Information Extension written by U.S. Atomic Energy Commission. Division of Technical Information and published by . This book was released on with total page 976 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : Chang Oh
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (316 download)
Download or read book Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-cooled Reactor Final Report written by Chang Oh and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The very high-temperature gas-cooled reactor (VHTR) is envisioned as a single- or dual-purpose reactor for electricity and hydrogen generation. The concept has average coolant temperatures above 9000C andoperational fuel temperatures above 12500C. The concept provides the potential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperature to support process heat applications, such as coal gasification, desalination or cogenerative processes, the VHTR's higher temperatures allow broader applications, including thermochemical hydrogen production. However, the very high temperatures of this reactor concept can be detrimental to safety if a loss-of-coolant accident (LOCA) occurs. Following the loss of coolant through the break and coolant depressurization, airwill enter the core through the break by molecular diffusion and ultimately by natural convection, leading to oxidation of the in-core graphite structure and fuel. The oxidation will accelerate heatup of the reactor core and the release of toxic gasses (CO and CO2) and fission products. Thus, without any effective countermeasures, a pipe break may lead to significant fuel damage and fission product release. Prior to the start of this Korean/United States collaboration, no computer codes were available that had been sufficiently developed and validated to reliably simulate a LOCA in the VHTR. Therefore, we have worked for the past three years on developing and validating advanced computational methods for simulating LOCAs in a VHTR. Research ObjectivesAs described above, a pipe break may lead to significant fuel damage and fission product release in the VHTR. The objectives of this Korean/United States collaboration were to develop and validate advanced computational methods for VHTR safety analysis. The methods that have been developed are now available to provide improved understanding of the VHTR during accidents.
Author : Chang Oh
Publisher :
ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (316 download)
Download or read book Development of Safety Analysis Codes and Experimental Validation for a Very High Temperature Gas-Cooled Reactor - FY-05 Annual Report written by Chang Oh and published by . This book was released on 2005 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The very high temperature gas-cooled reactors (VHTGRs) are those concepts that have average coolant temperatures above 9000C or operational fuel temperatures above 12500C. These concepts provide thepotential for increased energy conversion efficiency and for high-temperature process heat application in addition to power generation and nuclear hydrogen generation. While all the High Temperature Gas Cooled Reactor (HTGR) concepts have sufficiently high temperatures to support process heat applications, such as desalination and cogeneration, the VHTGR's higher temperatures are suitable for particular applications such as thermochemical hydrogen production. However, the high temperature operation can be detrimental to safety following a loss-of-coolant accident (LOCA) initiated by pipe breaks caused by seismic or other events. Following the loss of coolant through the break and coolant depressurization, air from the containment will enter the core by molecular diffusion and ultimately by natural convection, leading to oxidation of the in-core graphite structures and fuel. The oxidation will release heat and accelerate the heatup of the reactor core. Thus, without any effective countermeasures, a pipe break may lead to significant fuel damage and fission product release. The Idaho National Laboratory (INL) has investigated this event for the past three years forthe HTGR. However, the computer codes used, and in fact none of the world's computer codes, have been sufficiently developed and validated to reliably predict this event. New code development, improvement of the existing codes, and experimental validation are imperative to narrow the uncertainty in the predictions of this type of accident. The objectives of this Korean/United States collaboration are to develop advanced computational methods for VHTGR safety analysis codes and to validate these computer codes.
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ISBN 13 :
Total Pages : 1004 pages
Book Rating : 4.0/5 ( download)
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1965-07 with total page 1004 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ULTRA HIGH TEMPERATURE REACTOR EXPERIMENT (UHTREX) HAZARD REPORT. written by and published by . This book was released on 1962 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: UHTREX utilizes a high-temperature, He-cooled, graphite moderated reactor employing unclad, refractory fuel elements. The reactor is designed to produce a msximum thermal power of 3 Mw and a maximum exit He temperature of 2400 deg F. The purpose of the experimert is to evaluate the advantages of the simple fuel against the disadvantages of the associated operation of a contaminated coolant loop. The mechanical and nuclear design of the reactor and related apparatus are described, discussed, and evaluated from the standpoint of hazards associated with conduct of the experiment. The building design and characteristics of the site are also examined from the same standpoint. The probable effects of operational errors and component failures are studied. The conseqnences of credible accidents are not considered to be catastrophic for either operating personnel or personnel in surrounding areas. (auth).
Author :
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ISBN 13 :
Total Pages : 128 pages
Book Rating : 4.3/5 (91 download)
Download or read book Indexed Bibliography of Current Nuclear Safety Literature written by and published by . This book was released on 1965 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author :
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ISBN 13 :
Total Pages : 1022 pages
Book Rating : 4.0/5 ( download)
Download or read book U.S. Government Research & Development Reports written by and published by . This book was released on 1965 with total page 1022 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : L. F. Woods
Publisher :
ISBN 13 :
Total Pages : 58 pages
Book Rating : 4.:/5 (334 download)
Download or read book Zero-power Reactors, Safety and Accidents written by L. F. Woods and published by . This book was released on 1974 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Author : C. N. Kelber
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ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (143 download)
Download or read book Safety Analysis Report for the Argonne Advance Research Reactor Critical Experiment written by C. N. Kelber and published by . This book was released on 1965 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The hazards of zero-power critical experimentation utilizing a core of the proposed design of the Argonne Advanced Research Reactor (AARR) are reported. The design includes a central, hexagonal water-filled fluxtrap (each side 6 cm long) inside a modified fuel annulus containing 13.5 to 70.3 kg of highly enriched uranium, plus water moderator and stainless steel. A beryllium radial reflector is included. No unsafe conditions or undue hazard is associated with this facility.
