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Book Measurement of Fission Product Release During LWR Fuel Failure

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.

Book Fission product release Signatures for LWR Fuel Rods Failed During PCM and RIA Transients

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 Fission Product Processes In Reactor Accidents

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 Nuclear Safety in Light Water Reactors

Download or read book Nuclear Safety in Light Water Reactors written by Bal Raj Sehgal and published by Academic Press. This book was released on 2012-01-05 with total page 732 pages. Available in PDF, EPUB and Kindle. Book excerpt: La 4e de couverture indique : Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information.

Book Fission Product Release from Irradiated LWR Fuel Under Accident Conditions

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 Measurement and Characterization of Fission Products Released from LWR Fuel

Download or read book Measurement and Characterization of Fission Products Released from LWR Fuel written by and published by . This book was released on 1984 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Samples of commercial LWR fuel have been heated under simulated accident conditions to determine the extent and the chemical forms of fission product release. This project was sponsored by the USNRC under a broad program of reactor safety studies. Of the five tests discussed, the fractional releases of Kr, I, and Cs varied from approx. 2% at 1400°C to>50% at 2000°C; much smaller fractions of Ru, Ag, Sb, and Te were measured in some tests. The major chemical forms in the effluent appeared to include CsI, CsOH, Sb, Te, and Ag.

Book Fission Product Release from Simulated LWR Fuel Loss of Coolant Or Spent Fuel Transportation Accident Conditions

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 Measurement and Modelling of Postirradiation Fission Product Release from HTGR Fuel Particles Under Accident Conditions

Download or read book Measurement and Modelling of Postirradiation Fission Product Release from HTGR Fuel Particles Under 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 study was performed to provide a description of the release of fission products from failed fuel particles during a core heatup event in an HTGR. The need for this study was established in the Accident Initiation and Progression Analysis program. The release of fission products was measured from laser-failed BISO ThO2, TRISO UC2, and weak acid resin (WAR) particles over a range of burnups. The burnups were 0.25, 1.4 and 15.7% FIMA for ThO2 particles, 23.5 and 74% FIMA for UC2 particles, and 60% FIMA for WAR particles. The fission products measured were nuclides of xenon, iodine, krypton, tellurium, and cesium. Two types of experiments were performed: isothermal and temperature rise experiments. The range of the temperatures was from 1200° to 2300°C. In the temperature rise experiments, the heating rates were between 50° and 450°C/h.

Book Fission Gas Release in LWR Fuel Measured During Nuclear Operation

Download or read book Fission Gas Release in LWR Fuel Measured During Nuclear Operation 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 fuel behavior experiments are being conducted in the Heavy Boiling Water Reactor in Halden, Norway, to measure the release of Xe, Kr, and I fission products from typical light water reactor design fuel pellets. Helium gas is used to sweep the Xe and Kr fission gases out of two of the Instrumented Fuel Assembly 430 fuel rods and to a gamma spectrometer. The measurements of Xe and Kr are made during nuclear operation at steady state power, and for 135I following reactor scram. The first experiments were conducted at a burnup of 3000 MWd/t UO2, at bulk average fuel temperatures of approx. 850 K and approx. 23 kW/m rod power. The measured release-to-birth ratios (R/B) of Xe and Kr are of the same magnitude as those observed in small UO2 specimen experiments, when normalized to the estimated fuel surface-to-volume ratio. Preliminary analysis indicates that the release-to-birth ratios can be calculated, using diffusion coefficients determined from small specimen data, to within a factor of approx. 2 for the IFA-430 fuel. The release rate of 135I is shown to be approximately equal to that of 135Xe.

Book Fission Product Behavior During the PBF Severe Fuel Damage Test 1 1

Download or read book Fission Product Behavior During the PBF Severe Fuel Damage Test 1 1 written by Jack K. Hartwell and published by . This book was released on 1987 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Licensing Topical Report

Download or read book Licensing Topical Report written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The release of fission products from failed fuel particles was measured under simulated accident (core heatup) conditions. A generic model and specific model parameters that describe delayed fission product release from the kernels of failed HTGR fuel particles were developed from the experimental results. The release of fission products was measured from laser-failed BISO ThO2 and highly enriched (HEU) TRISO UC2 particles that had been irradiated to a range of kernel burnups. The burnups were 0.25, 1.4, and 15.7% FIMA for ThO2 particles and 23.5 and 74% FIMA for UC2 particles. The fission products measured were nuclides of xenon, iodine, krypton, tellurium, and cesium.

Book Review of Fuel Failures in Water Cooled Reactors 2006 2015 IAEA Nuclear Energy Series No Nf T 2 5

Download or read book Review of Fuel Failures in Water Cooled Reactors 2006 2015 IAEA Nuclear Energy Series No Nf T 2 5 written by International Atomic Energy Agency and published by . This book was released on 2019-12-19 with total page 65 pages. Available in PDF, EPUB and Kindle. Book excerpt: This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.