Fission-product-release Signatures for LWR Fuel Rods Failed During PCM and RIA Transients PDF Download
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Languages : en
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This paper discusses fission product release from light-water-reactor-type fuel rods to the coolant loop during design basis accident tests. One of the tests was a power-cooling-mismatch test in which a single fuel rod was operated in film boiling beyond failure. Other tests discussed include reactivity initiated accident (RIA) tests, in which the fuel rods failed as a result of power bursts that produced radial-average peak fuel enthalpies ranging from 250 to 350 cal/g. One of the RIA tests used two previously irradiated fuel rods. On-line gamma spectroscopic measurements of short-lived fission products, and important aspects of fission product behavior observed during the tests, are discussed. Time-dependent release fractions for short-lived fission products are compared with release fractions suggested by: the Reactor Safety Study; NRC Regulatory Guides; and measurements from the Three Mile Island accident. Iodine behavior observed during the tests is discussed, and fuel powdering is identified as a source of particulate fission product activity, the latter of which is neglected for most accident analyses.
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Languages : en
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This paper discusses fission product release from light-water-reactor-type fuel rods to the coolant loop during design basis accident tests. One of the tests was a power-cooling-mismatch test in which a single fuel rod was operated in film boiling beyond failure. Other tests discussed include reactivity initiated accident (RIA) tests, in which the fuel rods failed as a result of power bursts that produced radial-average peak fuel enthalpies ranging from 250 to 350 cal/g. One of the RIA tests used two previously irradiated fuel rods. On-line gamma spectroscopic measurements of short-lived fission products, and important aspects of fission product behavior observed during the tests, are discussed. Time-dependent release fractions for short-lived fission products are compared with release fractions suggested by: the Reactor Safety Study; NRC Regulatory Guides; and measurements from the Three Mile Island accident. Iodine behavior observed during the tests is discussed, and fuel powdering is identified as a source of particulate fission product activity, the latter of which is neglected for most accident analyses.
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Category : Power resources
Languages : en
Pages : 1744
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Category : Nuclear reactors
Languages : en
Pages : 760
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Author:
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 686
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Author: August W. Cronenberg
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Category : Light water reactors
Languages : en
Pages : 148
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Category : Technology & Engineering
Languages : en
Pages : 572
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Category :
Languages : en
Pages :
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Light water reactor (LWR) fuel rod behavior during transient experiments conducted in the Power Burst Facility is reviewed. The experiments examined simulated hypothetical reactivity initiated accidents (RIA) and power-cooling-mismatch (PCM) events. Fuel rod behavior calculated by the Fuel Rod Analysis Program-Transient (FRAP-T) is compared with the test data. Important physical phenomena observed during the tests and not presently incorporated into the FRAP-T code are: (a) fuel swelling in the radial direction due to fission gas effects, (b) UO2-zircaloy chemical interaction, and (c) loss of UO2 grain boundary strength and fuel powdering. Additional models needed in FRAP-T to reflect the fuel behavior observed during the two types of transients are cladding thickness variation during an RIA, molten fuel movement and possible cladding-molten fuel thermal interaction during a PCM event, and in the case of breached rods, the effects of hydrogen pickup on cladding embrittlement.
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Category :
Languages : en
Pages : 54
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On September 29, 1965, at 0150 a purposely defected partially molten fuel rod in the rupture loop test facility of the PRTR reactor failed in an unexpected manner. The rupture which resulted in a loss of about 30% of the UO2-PuO2 fuel from the rod was accompanied by the formation of a hole of approximately 1/2 inch diameter in the surrounding process tube. The subsequent flashing of the highly contaminated superheated water, released a fission product aerosol to the containment vessel atmosphere. This release resulted in about half of the noble gases reaching the containment vessel atmosphere. About 1 percent of the radioiodine and a somewhat smaller fraction of the solid fission products entered the containment vessel atmosphere. A subsequent radiochemical study provided detailed information on the behavior of some 15 fission products and of plutonium in their movement, following the rod failure, through the various liquid and gaseous systems of the reactor and its containment vessel. The ratios of the fission products (other than the noble gases) which were release to the containment vessel atmosphere were not far different from those in the fuel rod showing that relatively little fractionation occurred in the processes of dis- solution and aerosol formation. The observed deposition per unit area on metal surfaces was much higher than on painted surfaces. Much of the behavior of the radionuclides in this system was similar to what might be expected in the melt-down of any water cooled reactor and the information gained from the study should be applicable to the design of safeguards for such events.
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Category : Research
Languages : en
Pages : 1220
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Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.
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Category : Science
Languages : en
Pages : 228
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