Fission Product Release and Fuel Cladding Interaction in Severe-accident Tests of LWR Fuel

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Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Fission Product Release and Fuel Cladding Interaction in Severe-accident Tests of LWR Fuel by :

Download or read book Fission Product Release and Fuel Cladding Interaction in Severe-accident Tests of LWR Fuel written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The examination of these samples indicated a correlation between the posttest fuel microstructure and the fission product release during the test. As expected, structural changes in the fuel and fission product release increased with test temperature. The effect of steam flow rate, which controls the extent of cladding oxidation, however, was less clear. The amount of fuel-cladding reaction and liquefaction was greatest in the test with a low steam flow rate, which was also the highest temperature test. Other data indicate, however, that extensive fuel-cladding reaction and liquefaction would be expected at approx. 1700°C with reduced steam flow rate (i.e., with reduced oxidation). The similar gas release values and fuel microstructures for the 1700 and 2000°C test are somewhat surprising, but may indicate the influence of the steam conditions on gas release as well as on fuel-cladding reaction. The extent of fuel-cladding interaction in these tests, and the resulting intermediate phases, appear to be consistent with the observations of Hofmann and Kerwin-Peck.

Modeling and Experiment of Fission Products Release and Interaction with Coolant for Defective Fuel in Light Water Reactor (LWR)

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ISBN 13 :
Total Pages : 102 pages
Book Rating : 4.:/5 (1 download)

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Book Synopsis Modeling and Experiment of Fission Products Release and Interaction with Coolant for Defective Fuel in Light Water Reactor (LWR) by : Sha Xue

Download or read book Modeling and Experiment of Fission Products Release and Interaction with Coolant for Defective Fuel in Light Water Reactor (LWR) written by Sha Xue and published by . This book was released on 2017 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt: During the normal operation of light water reactor, fuel defects can reside on fuel cladding from various reason such as fuel-pellet mechanical interaction, the hydriding of the Zr clad, the grid fritting from the assembly support, the warp wire fritting with the clad and also the stress corrosion cracking (SCC). The formation of defects on fuel cladding will result water ingression to the gap and react with nuclear fuel and the cladding inner surface. The interaction of water and nuclear fuel will affect the fuel thermal properties and deteriorate the cladding by hydriding and change of oxygen potential in the fuel. The change of fuel thermal properties will decrease the thermal conductivity, lead the decrease of heat transfer coefficient which may increase the fuel melting risk. The volatile fission products and fission gas will release to the coolant through cladding defects and increase the coolant activity and the defective nuclear fuel becomes a fission product source term when reactor is under normal operation. Experimental and modeling are applied to understand the behavior of a defective fuel pin. The experimental part focuses on the dissolution test of rare earth fission products in simulated LWR coolant chemistry and the diffusion coefficient measurement of cesium iodide in simulated LWR coolant chemistry using Nuclear Magnetic Resonance (NMR) technique. Rare earth fission products significantly contribute the residual heat and large quantity of radioactivity after the core shut down or in severe accident, therefore, their dissolution kinetic parameters in LWR are important to reactor safety and the understanding the source terms.

Fission Product Release from Simulated LWR Fuel. [Loss of Coolant Or Spent Fuel Transportation Accident Conditions].

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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.

Overview of the U.S. DOE Accident Tolerant Fuel Development Program

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (967 download)

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Book Synopsis Overview of the U.S. DOE Accident Tolerant Fuel Development Program by :

Download or read book Overview of the U.S. DOE Accident Tolerant Fuel Development Program written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The United States Fuel Cycle Research and Development Advanced Fuels Campaign has been given the responsibility to conduct research and development on enhanced accident tolerant fuels with the goal of performing a lead test assembly or lead test rod irradiation in a commercial reactor by 2022. The Advanced Fuels Campaign has defined fuels with enhanced accident tolerance as those that, in comparison with the standard UO2-Zircaloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations and operational transients, as well as design-basis and beyond design-basis events. This paper provides an overview of the FCRD Accident Tolerant Fuel program. The ATF attributes will be presented and discussed. Attributes identified as potentially important to enhance accident tolerance include reduced hydrogen generation (resulting from cladding oxidation), enhanced fission product retention under severe accident conditions, reduced cladding reaction with high-temperature steam, and improved fuel-cladding interaction for enhanced performance under extreme conditions. To demonstrate the enhanced accident tolerance of candidate fuel designs, metrics must be developed and evaluated using a combination of design features for a given LWR design, potential improvements to that design, and the design of an advanced fuel/cladding system. The aforementioned attributes provide qualitative guidance for parameters that will be considered for fuels with enhanced accident tolerance. It may be unnecessary to improve in all attributes and it is likely that some attributes or combination of attributes provide meaningful gains in accident tolerance, while others may provide only marginal benefits. Thus, an initial step in program implementation will be the development of quantitative metrics. A companion paper in these proceedings provides an update on the status of establishing these quantitative metrics for accident tolerant LWR fuel. 1 The United States FCRD Advanced Fuels Campaign has embarked on an aggressive schedule for development of enhanced accident tolerant LWR fuels. The goal of developing such a fuel system that can be deployed in the U.S. LWR fleet in the next 10 to 20 years supports the sustainability of clean nuclear power generation in the United States.

Nuclear Safety in Light Water Reactors

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Publisher : Academic Press
ISBN 13 : 0123884462
Total Pages : 732 pages
Book Rating : 4.1/5 (238 download)

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Book Synopsis Nuclear Safety in Light Water Reactors by : Bal Raj Sehgal

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.

Proceedings of the Symposium on Chemical Phenomena Associated with Radioactivity Releases During Severe Nuclear Plant Accidents

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ISBN 13 :
Total Pages : 730 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Proceedings of the Symposium on Chemical Phenomena Associated with Radioactivity Releases During Severe Nuclear Plant Accidents by : S. J. Niemczyk

Download or read book Proceedings of the Symposium on Chemical Phenomena Associated with Radioactivity Releases During Severe Nuclear Plant Accidents written by S. J. Niemczyk and published by . This book was released on 1987 with total page 730 pages. Available in PDF, EPUB and Kindle. Book excerpt:

NUREG/CR.

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ISBN 13 :
Total Pages : 48 pages
Book Rating : 4.:/5 (319 download)

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Book Synopsis NUREG/CR. by : U.S. Nuclear Regulatory Commission

Download or read book NUREG/CR. written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1977 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Energy Research Abstracts

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ISBN 13 :
Total Pages : 922 pages
Book Rating : 4.3/5 (129 download)

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Book Synopsis Energy Research Abstracts by :

Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 922 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Heat and Mass Transfer in Severe Nuclear Reactor Accidents

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Publisher : Begell House Publishers
ISBN 13 : 9781567000597
Total Pages : 708 pages
Book Rating : 4.0/5 (5 download)

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Book Synopsis Heat and Mass Transfer in Severe Nuclear Reactor Accidents by : J. T. Rogers

Download or read book Heat and Mass Transfer in Severe Nuclear Reactor Accidents written by J. T. Rogers and published by Begell House Publishers. This book was released on 1996-01-01 with total page 708 pages. Available in PDF, EPUB and Kindle. Book excerpt: Papers and lectures from an international seminar on various heat and mass transfer aspects involved in severe accidents in nuclear power reactors.

Reactor Safety Research Semiannual Report

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ISBN 13 :
Total Pages : 72 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Reactor Safety Research Semiannual Report by :

Download or read book Reactor Safety Research Semiannual Report written by and published by . This book was released on 1985 with total page 72 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Metal-water Reactions

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ISBN 13 :
Total Pages : 58 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Metal-water Reactions by : K. M. Horst

Download or read book Metal-water Reactions written by K. M. Horst and published by . This book was released on 1959 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Measurement of Fission Product Release During LWR Fuel Failure

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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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.

ERDA Energy Research Abstracts

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Publisher :
ISBN 13 :
Total Pages : 1048 pages
Book Rating : 4.:/5 (31 download)

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Book Synopsis ERDA Energy Research Abstracts by :

Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1983 with total page 1048 pages. Available in PDF, EPUB and Kindle. Book excerpt:

An Assessment of LWR Fuel-failure Propagation Potential

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Publisher :
ISBN 13 :
Total Pages : 148 pages
Book Rating : 4.3/5 (91 download)

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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:

A Scoping Study of Spent Fuel Cask Transportation Accidents

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ISBN 13 :
Total Pages : 172 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis A Scoping Study of Spent Fuel Cask Transportation Accidents by : W. R. Rhyne

Download or read book A Scoping Study of Spent Fuel Cask Transportation Accidents written by W. R. Rhyne and published by . This book was released on 1979 with total page 172 pages. Available in PDF, EPUB and Kindle. Book excerpt: A scoping study of spent fuel cask transportation accidents was performed to provide the NRC with an assessment of existing information and to recommend, on a priority basis, the additional information that should be obtained to allow specification of increasingly realistic source terms. The scope was limited to the escape of radionuclides from the cask to the environment resulting from severe accidents. The accident environment definition associated with a severe accident is the starting point and was selected not for its realism but to allow sensitivity studies on the remaining variables in the accident scenario. However, given this accident definition, the remainder of the evaluation of the accident scenarios is to be as realistic as possible. Information was found to be inadequate to make correlations between accident severity and radionuclide release. Generally, cask and fuel rod thermal-hydraulic data and analytical capability were found to be reasonably adequate; however, data and analytical capability for evaluating structural response to impact are not. Radionuclide behavior information is adequate for noble gases but generally inadequate for most volatile radionuclides and for fuel particulates. A series of gauging calculations were performed to permit prioritization of the information needs, and research recommendations were made in eight areas.

Power Burst Facility (PBF) Severe Fuel Damage Test 1-4 Test Results Report

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ISBN 13 :
Total Pages : 0 pages
Book Rating : 4.:/5 (16 download)

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Book Synopsis Power Burst Facility (PBF) Severe Fuel Damage Test 1-4 Test Results Report by :

Download or read book Power Burst Facility (PBF) Severe Fuel Damage Test 1-4 Test Results Report written by and published by . This book was released on 1989 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: A comprehensive evaluation of the Severe Fuel Damage (SFD) Test 1-4 performed in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory is presented. Test SFD 1-4 was the fourth and final test in an internationally sponsored light water reactor severe accident research program, initiated by the US Nuclear Regulatory Commission. The overall technical objective of the test was to contribute to the understanding of fuel and control rod behavior, aerosol and hydrogen generation, and fission product release and transport during a high-temperature, severe fuel damage transient. A test bundle, comprised of 26 previously irradiated (36,000 MWd/MtU) pressurized water-reactor-type fuel rods, 2 fresh instrumented fuel rods, and 4 silver-indium-cadmium control rods, was surrounded by an insulating shroud and contained in a pressurized in-pile tube. The experiment consisted of a 1.3-h transient at a coolant pressure of 6.95 MPa in which the inlet coolant flow to the bundle was reduced to 0.6 g/s while the bundle fission power was gradually increased until dryout, heatup, cladding rupture, and oxidation occurred. With sustained fission power and heat from oxidation, temperatures continued to rise rapidly, resulting in zircaloy and control rod absorber alloy melting, fuel liquefaction, material relocation, and the release of hydrogen, aerosols, and fission products. The transient was terminated over a 2100-s time span by slowly reducing the reactor power and cooling the damaged bundle with argon gas. A description and evaluation of the major phenomena, based upon the response of on-line instrumentation, analysis of fission product and aerosol data, postirradiation examination of the fuel bundle, and calculations using the SCDAP/RELAP5 computer code, are presented. 40 refs., 160 figs., 31 tabs.

Chemical Thermodynamics of Complex Systems

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (727 download)

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Book Synopsis Chemical Thermodynamics of Complex Systems by :

Download or read book Chemical Thermodynamics of Complex Systems written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A detailed thermodynamic assessment has been made of the chemical reactions of fission products in LWR fuel rods. Using recent thermodynamic data and the in-reactor oxygen potential and temperature range of LWRs, equilibrium thermodynamic calculations were performed for the most plausible reactions of the fission products. The emphasis in this model is on the chemistry of cesium and rubidium and their reactions with the fuel, other fission products, and the zircaloy cladding. The model predictions are discussed for their implications in fuel-cladding interactions.