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Modeling Fission Product Release From Ruptured Lwr Fuel Rods
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Book Synopsis Modeling Fission Product Release from Ruptured LWR Fuel Rods by :
Download or read book Modeling Fission Product Release from Ruptured LWR Fuel Rods written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The principal objectives of the fission product release program are to determine the quantity of radiologically significant fission products released from defected LWR fuel rods under accident conditions, identify their chemical and physical forms, and interpret the results for use as input to computer models of postulated transportation and loss-of-coolant accidents. Experimental work with flowing steam in the temperature range 500 to 1200°C and with dry air at 500°C and 700°C has been completed. One series of tests, the Implant Test Series, employed simulated fission products which were coated on unirradiated UO2 fuel pellets; a second series, the Low Burnup Fuel Test Series, used fuel capsules irradiated to 1000 MWd/MT at high heat rating (560 to 660 W/cm), and a third series of experiments, the High Burnup Test Series, used fuel irradiated to 30,000 MWd/MT in the H.B. Robinson reactor at low heat rating (175 to 320 W/cm). Sufficient analytical results have been obtained to permit the formulation of a preliminary empirical model for cesium release in steam. The model assumes that cesium release is the sum of two components: burst release (that carried out with escaping plenum gas when the rod ruptures) and diffusion release (that diffusing from the gap space after the plenum gas has vented).
Book Synopsis Fission Product Release from BWR Fuel Under LOCA Conditions by :
Download or read book Fission Product Release from BWR Fuel Under LOCA Conditions written by and published by . This book was released on 1981 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission Product Release from Defected LWR Fuel Rods by :
Download or read book Fission Product Release from Defected LWR Fuel Rods written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Experiments conducted at Oak Ridge National Laboratory both with fission product simulants and with irradiated commercial fuel have been utilized to develop a semi-empirical model of fission product release from defected Light Water Reactor (LWR) fuel rods. At fuel temperatures less than 1200°C, releases occur from fission products previously accumulated in the pellet-to-cladding gap region. In this temperature range, the release of species of moderate volatility is postulated to result from two processes. The first of these, which occurs during the period of fuel clad rupture, is due to the transport of the fill and fission product gases as they are vented through the cladding defect. The second mechanism for release, which is time-dependent, involves the diffusional transport of the semi-volatile species to the point of clad rupture through the interconnected voids (the pellet-to-cladding gap and cracks in fuel pellets) within the fuel rod.
Book Synopsis Fission Product Release from High Gap-inventory LWR Fuel Under LOCA Conditions by :
Download or read book Fission Product Release from High Gap-inventory LWR Fuel Under LOCA Conditions written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission product release tests were performed with light water reactor (LWR) fuel rod segments containing large amounts of cesium and iodine in the pellet-to-cladding gap space in order to check the validity of the previously published Source Term Model for this type of fuel. The model describes the release of fission product cesium and iodine from LWR fuel rods for controlled loss-of-coolant accident (LOCA) transients in the temperature range 500 to 1200°C. The basis for the model was test data obtained with simulated fuel rods and commercial fuel irradiated to high burnup but containing relatively small amounts of cesium and iodine in the pellet-to-cladding gap space.
Book Synopsis Quarterly Progress Report on Fission Product Behavior in LWRs for the Period ... by :
Download or read book Quarterly Progress Report on Fission Product Behavior in LWRs for the Period ... written by and published by . This book was released on 1979 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission Product Source Terms for the LWR Loss-of-coolant Accident by :
Download or read book Fission Product Source Terms for the LWR Loss-of-coolant Accident written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Models for cesium and iodine release from light-water reactor (LWR) fuel rods failed in steam were formulated based on experimental fission product release data from several types of failed LWR fuel rods. The models were applied to a pressurized water reactor (PWR) undergoing a hypothetical loss-of-coolant accident (LOCA) temperature transient. Calculated total iodine and cesium releases from the fuel rods were 0.053 and 0.025% of the total reactor inventories of these elements, respectively, with most of the release occurring at the time of rupture. These values are approximately two orders of magnitude less than releases used in WASH-1400, the Reactor Safety Study.
Book Synopsis Fission Product Release from Highly Irradiated LWR Fuel by :
Download or read book Fission Product Release from Highly Irradiated LWR Fuel written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of experiments was conducted with highly irradiated light-water reactor fuel rod segments to investigate fission products released in steam in the temperature range 500 to 1200°C. (Two additional release tests were conducted in dry air.) The primary objectives were to quantify and characterize fission product release under conditions postulated for a spent-fuel transportation accident and for a successfully terminated loss-of-coolant accident (LOCA). In simulated, controlled LOCA-type tests, release at the time of rupture proved to be more significant than the diffusional release that followed. Comparison of the release data for the dry-air tests with the release data of similarly conducted tests in steam indicated significant increases in the releases of iodine, ruthenium, and cesium in air. Various parameters that affect fission product release are discussed, and experimental observations and analysis of the chemical behavior of releasable fission products in inert, steam, and dry-air atmospheres are examined.
Book Synopsis A Model for Fission-gas Release from Porous Fuels in Low-permeability Containers by : John W. Prados
Download or read book A Model for Fission-gas Release from Porous Fuels in Low-permeability Containers written by John W. Prados and published by . This book was released on 1961 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission Product Release from LWR Fuel Defected in Steam in the Temperature Range 500 to 1600/sup 0/C. by :
Download or read book Fission Product Release from LWR Fuel Defected in Steam in the Temperature Range 500 to 1600/sup 0/C. written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: For practical purposes the release of cesium and iodine from LWR fuel rods in the temperature range 500 to 1600/sup 0/C can be considered to originate from three sources: (1) the gap inventory with release by both burst (vented gas) and diffusion; (2) grain boundary with release by tunnel formation; and (3) UO/sub 2/ matrix with release by solid state diffusion. The chemical behavior of released iodine and cesium (at least after contact with steam) is predominantly that of CsI and CsOH. Fission gas release is the sum of the plenum inventory, gas embedded in the fuel and cladding surface layers and that released by tunnel formation, and solid state diffusion from the UO/sub 2/ matrix. A small amount of large particle-sized fuel dust is ejected at time of rupture.
Book Synopsis Fission Product Release from LWR Fuel Defected in Steam in the Temperature Range 500 to 1600°C. by :
Download or read book Fission Product Release from LWR Fuel Defected in Steam in the Temperature Range 500 to 1600°C. written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: For practical purposes the release of cesium and iodine from LWR fuel rods in the temperature range 500 to 1600°C can be considered to originate from three sources: (1) the gap inventory with release by both burst (vented gas) and diffusion; (2) grain boundary with release by tunnel formation; and (3) UO2 matrix with release by solid state diffusion. The chemical behavior of released iodine and cesium (at least after contact with steam) is predominantly that of CsI and CsOH. Fission gas release is the sum of the plenum inventory, gas embedded in the fuel and cladding surface layers and that released by tunnel formation, and solid state diffusion from the UO2 matrix. A small amount of large particle-sized fuel dust is ejected at time of rupture.
Book Synopsis An Assessment of LWR Fuel-failure Propagation Potential by : August W. Cronenberg
Download or read book An Assessment of LWR Fuel-failure Propagation Potential written by August W. Cronenberg and published by . This book was released on 1980 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fission-product-release Signatures for LWR Fuel Rods Failed During PCM and RIA Transients by :
Download or read book Fission-product-release Signatures for LWR Fuel Rods Failed During PCM and RIA Transients written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Fission Product Processes In Reactor Accidents by : J. T. Rogers
Download or read book Fission Product Processes In Reactor Accidents written by J. T. Rogers and published by CRC Press. This book was released on 2020-12-17 with total page 883 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Fission Product Release from Irradiated LWR Fuel Under Accident Conditions by :
Download or read book Fission Product Release from Irradiated LWR Fuel Under Accident Conditions written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Fission product release from irradiated LWR fuel is being studied by heating fuel rod segments in flowing steam and an inert carrier gas to simulate accident conditions. Fuels with a range of irradiation histories are being subjected to several steam flow rates over a wide range of temperatures. Fission product release during each test is measured by gamma spectroscopy and by detailed examination of the collection apparatus after the test has been completed. These release results are complemented by a detailed posttest examination of samples of the fuel rod segment. Results of release measurements and fuel rod characterizations for tests at 1400 through 2000°C are presented in this paper.
Book Synopsis Fission Product Release from Simulated LWR Fuel. [Loss of Coolant Or Spent Fuel Transportation Accident Conditions]. by :
Download or read book Fission Product Release from Simulated LWR Fuel. [Loss of Coolant Or Spent Fuel Transportation Accident Conditions]. written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of tests has been conducted with simulated LWR fuel as part of a program for determining the quantities and characteristics of radiologically significant fission products that can be released under postulated spent-fuel transportation accident (SFTA) conditions and successfully terminated loss-of-coolant accident (LOCA) conditions. These tests were performed in either flowing-steam or dry-air atmospheres with Zircaloy-4-clad fuel-rod segments that contained unirradiated UO2 pellets coated with radioactively traced CsOH, CsI, and TeO2. A summary of the test conditions and amounts released are given. Cesium release associated with the implanted CsOH appeared to be limited by the formation of low-volatility uranate compounds. Iodine release was observed primarily as CsI, but also as I2; in addition, at test temperatures of 900°C and above, significant migration of the CsI to the cooler ends of the fuel-rod segments was noted. Tellurium release was markedly restricted by rapid reaction with the Zircaloy cladding. The tests in air yielded enhanced releases of cesium and iodine, and considerable swelling of the oxidized UO2. As anticipated, measured release fractions were greater when the test rods were ruptured at temperature by internal pressure than when the cladding failures were machined in the rods prior to testing.
Book Synopsis Assessment of FRAPCON-1 BE/EM Calculated Fission Gas Release in RISO Fuel Rods by : Rosanna Chambers
Download or read book Assessment of FRAPCON-1 BE/EM Calculated Fission Gas Release in RISO Fuel Rods written by Rosanna Chambers and published by . This book was released on 1980 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Measurement of Fission Product Release During LWR Fuel Failure by :
Download or read book Measurement of Fission Product Release During LWR Fuel Failure written by and published by . This book was released on 1979 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The PBF is a specialized test reactor consisting of an annular core and a central test space 21 cm in diameter and 91 cm high. A test loop circulates coolant through the central experimental section at typical power reactor conditions. Light-water-reactor-type fuel rods are exposed to power bursts simulating reactivity insertion transients, and to power-cooling-mismatch conditions during which the rods are allowed to operate in film boiling. Fission product concentrations in the test loop coolant are continuously monitored during these transients by a Ge(Li) detector based gamma spectrometer. Automatic batch processing of pulse height spectra results in a list of radionuclide concentrations present in the loop coolant as a function of time during the test. Fission product behavior is then correlated to test parameters and posttest examination of the fuel rods. Data are presented from Test PCM-1.
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