In-vessel Zircaloy Oxidation/hydrogen Generation Behavior During Severe Accidents PDF Download
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Author: August W. Croneberg
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages :
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Author: August W. Croneberg
Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages :
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Author:
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Category :
Languages : en
Pages :
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In-vessel Zircaloy oxidation and hydrogen generation data from various US Nuclear Regulatory Commission severe-fuel damage test programs are presented and compared, where the effects of Zircaloy melting, bundle reconfiguration, and bundle quenching by reflooding are assessed for common findings. The experiments evaluated include fuel bundles incorporating fresh and previously irradiated fuel rods, as well as control rods. Findings indicate that the extent of bundle oxidation is largely controlled by steam supply conditions and that high rates of hydrogen generation continued after melt formation and relocation. Likewise, no retardation of hydrogen generation was noted for experiments which incorporated control rods. Metallographic findings indicate extensive oxidation of once-molten Zircaloy bearing test debris. Such test results indicate no apparent limitations to Zircaloy oxidation for fuel bundles subjected to severe-accident coolant-boiloff conditions. 46 refs., 22 figs., 12 tabs.
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Category :
Languages : en
Pages :
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The PBF Severe Fuel Damage tests will provide a unique opportunity to address several reactor safety issues. These experiments will simulate severe accidents which include fuel behavior similar to the TMI accident. Rod damage mechanisms, fuel rod fragmentation, rubble bed formation, hydrogen generation and fission product release are among the important phenomena which will be investigated. The on-line hydrogen measurements, supplemented with analyses of grab samples will provide data to evaluate zircaloy oxidation models and define hydrogen behavior during accidents.
Author:
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Category : Power resources
Languages : en
Pages : 444
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Author: August W. Cronenberg
Publisher:
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Category : Light water reactors
Languages : en
Pages : 106
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Category :
Languages : en
Pages :
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Oxidation of Zircaloy cladding is the primary source of hydrogen generated during a degraded-core accident. In this paper, reported Zircaloy oxidation rates, either measured at 1500 to 1850°C or extrapolated from the low-temperature data obtained at 1500°C, are critically reviewed with respect to their applicability to a degraded-core accident situation in which the high-temperature fuel cladding is likely to be exposed to and oxidized in mixtures of hydrogen and depleted steam, rather than in an unlimited flux of pure steam. New results of Zircaloy oxidation measurements in various mixtures of hydrogen and steam are reported for1500°C. The results show significantly smaller oxidation and, hence, hydrogen-generation rates in the mixture, compared with those obtained in pure steam. It is also shown that a significant fraction of hydrogen, generated as a result of Zircaloy oxidation, is dissolved in the cladding material itself, which prevents that portion of hydrogen from reaching the containment building space. Implications of these findings are discussed in relation to a more realistic method of quantifying the hydrogen source term for a degraded-core accident analysis.
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Category : Government publications
Languages : en
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Author:
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Category : Government publications
Languages : en
Pages : 1064
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Author: J. T. Rogers
Publisher: CRC Press
ISBN: 1000158624
Category : Science
Languages : en
Pages : 742
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The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.
Author: Paul D. Bayless
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 172
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