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Book Synopsis Electrically Heated Ex-reactor Pellet-cladding Interaction (PCI) Simulations Utilizing Irradiated Zircaloy Cladding by : J. O. Barner
Download or read book Electrically Heated Ex-reactor Pellet-cladding Interaction (PCI) Simulations Utilizing Irradiated Zircaloy Cladding written by J. O. Barner and published by . This book was released on 1985 with total page 124 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Electrically Heated Ex-reactor Pellet-cladding Interaction (PCI) Simulations Utilizing Irradiated Zircaloy Cladding. [PWR]. by :
Download or read book Electrically Heated Ex-reactor Pellet-cladding Interaction (PCI) Simulations Utilizing Irradiated Zircaloy Cladding. [PWR]. written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: In a program sponsored by the Fuel Systems Research Branch of the US Nuclear Regulatory Commission, a series of six electrically heated fuel rod simulation tests were conducted at Pacific Northwest Laboratory. The primary objective of these tests was to determine the susceptibility of irradiated pressurized-water reactor (PWR) Zircaloy-4 cladding to failures caused by pellet-cladding mechanical interaction (PCMI). A secondary objective was to acquire kinetic data (e.g., ridge growth or relaxation rates) that might be helpful in the interpretation of in-reactor performance results and/or the modeling of PCMI. No cladding failures attributable to PCMI occurred during the six tests. This report describes the testing methods, testing apparatus, fuel rod diametral strain-measuring device, and test matrix. Test results are presented and discussed.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 524 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Experimental Support and Development of Single-rod Fuel Codes Program by : D. D. Lanning
Download or read book Experimental Support and Development of Single-rod Fuel Codes Program written by D. D. Lanning and published by . This book was released on 1987 with total page 64 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Government Reports Announcements & Index by :
Download or read book Government Reports Announcements & Index written by and published by . This book was released on 1985-05 with total page 588 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Government Reports Annual Index by :
Download or read book Government Reports Annual Index written by and published by . This book was released on 1985 with total page 878 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fracture Behavior of Zircaloy Spent-fuel Cladding by :
Download or read book Fracture Behavior of Zircaloy Spent-fuel Cladding written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Zircaloy cladding of water reactor fuel rods is susceptible to local breach-type failure, commonly known as pellet-cladding interaction (PCI) failure, during operational and off-normal power transients after the fuel has achieved a sufficiently high burnup. An optimization of power ramp procedures or fuel rod fabrication to minimize the cladding failure would result in a significant decrease in radiation exposure of plant personnel due to background and airborne radioactivity as well as an extension of core life in terms of allowable off-gas radioactivity. As part of a program to provide a better understanding of the fuel rod faiure phenomenon and to facilitate the formulation of a better failure criterion, a mechanistic study of the deformation and fracture behavior of high-burnup spent-fuel cladding is in progress under simulated PCI conditions.
Book Synopsis Title List of Documents Made Publicly Available by :
Download or read book Title List of Documents Made Publicly Available written by and published by . This book was released on with total page 936 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book INIS Atomindex written by and published by . This book was released on 1985 with total page 952 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Government Reports Annual Index: Keyword A-L by :
Download or read book Government Reports Annual Index: Keyword A-L written by and published by . This book was released on 1985 with total page 976 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Structure of High-burnup-fuel Zircaloy Cladding. [PWR ; BWR]. by :
Download or read book Structure of High-burnup-fuel Zircaloy Cladding. [PWR ; BWR]. written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Zircaloy cladding from high-burnup (> 20 MWd/kg U) fuel rods in light-water reactors is characterized by a high density of irradiation-induced defects (RID), compositional changes (e.g., oxygen and hydrogen uptake) associated with in-service corrosion, and geometrical changes produced by creepdown, bowing, and irradiation-induced growth. During a reactor power transient, the cladding is subject to localized stress imposed by thermal expansion of the cracked fuel pellets and to mechanical constraints imposed by pellet-cladding friction. As part of a program to provide a better understanding of brittle-type failure of Zircaloy fuel cladding by pellet-cladding interaction (PCI) phenomenon, the stress-rupture properties and microstructural characteristics of high-burnup spent fuel cladding have been under investigation. This paper reports the results of the microstructural examinations by optical microscopy, scanning (SEM), 100-keV transmission (TEM), and 1 MeV high-voltage (HVEM) electron microscopies of the fractured spent fuel cladding with a specific empahsis on a correlation of the structural characteristics with the fracture behavior.
Book Synopsis Tube-Burst Response of Irradiated Zircaloy Spent-Fuel Cladding by : AA. Bauer
Download or read book Tube-Burst Response of Irradiated Zircaloy Spent-Fuel Cladding written by AA. Bauer and published by . This book was released on 1979 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Transient-heating tube-burst tests were conducted on a 50.8-cm length of Zircaloy cladding obtained from spent-fuel rods irradiated in the H. B. Robinson power reactor to a peak burn-up of 30 MWD/kg. Internal electrical resistance heaters were used to achieve nominal heating rates of 28°C/s for the tests. The tests were conducted in steam and the independent experimental variable was the initial level of helium pressurization.
Book Synopsis Transactions of the Eleventh Water Reactor Safety Research Information Meeting by :
Download or read book Transactions of the Eleventh Water Reactor Safety Research Information Meeting written by and published by . This book was released on 1983 with total page 392 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions by :
Download or read book Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions written by and published by . This book was released on 2001 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Specimen geometries have been developed to determine the mechanical properties of irradiated Zircaloy cladding subjected to the mechanical conditions and temperatures associated with reactivity-initiated accidents (RIA) and loss-of-coolant accidents (LOCA). Miniature ring-stretch specimens were designed to induce both uniaxial and plane-strain states of stress in the transverse (hoop) direction of the cladding. Also, longitudinal tube specimens were also designed to determine the constitutive properties in the axial direction. Finite-element analysis (FEA) and experimental parameters and results were closely coupled to optimize an accurate determination of the stress-strain response and to induce fracture behavior representative of accident conditions. To determine the constitutive properties, a procedure was utilized to transform measured values of load and displacement to a stress-strain response under complex loading states. Additionally, methods have been developed to measure true plastic strains in the gauge section and the initiation of failure using real-time data analysis software. Strain rates and heating conditions have been selected based on their relevance to the mechanical response and temperatures of the cladding during the accidents.
Book Synopsis Progress on Pellet-Cladding Interaction and Stress Corrosion Cracking by : International Atomic Energy Agency
Download or read book Progress on Pellet-Cladding Interaction and Stress Corrosion Cracking written by International Atomic Energy Agency and published by . This book was released on 2021-08-15 with total page 312 pages. Available in PDF, EPUB and Kindle. Book excerpt: Flexible operation and related power changes can have a direct impact on fuel integrity through pellet-cladding interaction/stress corrosion cracking (PCI/SCC) phenomena, which could lead to fuel failures in certain conditions.
Book Synopsis Verslagen en verhandelingen by : Nationaal Lucht- en Ruimtevaartlaboratorium (Netherlands)
Download or read book Verslagen en verhandelingen written by Nationaal Lucht- en Ruimtevaartlaboratorium (Netherlands) and published by . This book was released on 1985 with total page 938 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Zircaloy-4 Cladding Deformation During Power Reactor Irradiation by : DG. Franklin
Download or read book Zircaloy-4 Cladding Deformation During Power Reactor Irradiation written by DG. Franklin and published by . This book was released on 1982 with total page 33 pages. Available in PDF, EPUB and Kindle. Book excerpt: The four primary Zircaloy fuel cladding deformation phenomena--axial elongation, circumferential creep, ovalization, and ridging--have been investigated for fuel irradiated in four modern pressurized water reactors. The axial elongation of fueled and nonfueled rods is examined by a regression fit for dependence on fluence, clad texture, yield stress, applied stress and, for fuel rods, fuel pellet length to diameter ratio. For fueled rods, only fluence and stress are found to be important, although the range of texture data is small. For nonfueled rods, the texture is found to influence elongation.
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