Download or read book High pressurization rate burst test of hydrided Zircaloy 4 fuel cladding at room temperature written by Fumihisa Nagase and published by . This book was released on 1998 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book High pressurization rate burst test of hydrided zircaloy 4 fuel cladding at 620 K written by Fumihisa Nagase and published by . This book was released on 2000 with total page 31 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 1396 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Experimental and Analytical Investigation of the Mechanical Behavior of High Burnup Zircaloy 4 Fuel Cladding written by Robert S. Daum and published by . This book was released on 2008 with total page 22 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sufficient mechanical ductility of high-burnup Zircaloy-4 fuel cladding is important to prevent large-opening ruptures and significant fuel dispersal during postulated in-reactor and spent-fuel processing accidents. The effect of irradiation, oxidation, and hydriding at high fuel burnup may degrade cladding ductility to the extent that such large ruptures are possible under severe loadings. To understand this susceptibility to failure, this study focused on mechanical testing coupled with detailed finite-element modeling and analyses. Under ring-compression-type loading at room temperature, tensile cracks form within the corrosion-induced oxide layer under elastic loading. The oxide crack then propagates into the cladding wall under additional loading with little to no measurable plastic strain, as confirmed by both experiment and analyses of plastic hoop strain in the ring. For cladding with the oxide removed prior to testing at ≤1 %/s, cracking of the underlying hydride rim comprised of circumferentially oriented hydrides occurs at low plastic hoop strain (≤3 %), whereas the finite-element analysis suggests that the base alloy with a relatively small amount of hydrides appears to fail at higher strain (>8 %). At even higher strain rates (≈400 %/s), cracking within the hydride rim occurs at near-zero ductility, but the base alloy continues to remain highly ductile. These room-temperature results indicate that the hydride rim is sensitive to strain rate, whereas the base alloy is relatively not. With the precipitation of ≈100 % radially oriented hydrides, the cladding exhibits near-zero ductility at room temperature and ≈0.1 %/s. This study suggests that the ring-compression test coupled with finite-element modeling and analysis may be used to estimate crack-initiation strains in irradiated cladding materials with susceptible microstructures and under various deformation rates.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1970-10 with total page 1028 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1969 with total page 368 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1983 with total page 1474 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Comparison of Transient Heating Burst Test Results of Unirradiated and Irradiated Zircaloy 4 Fuel Rod Cladding written by LM. Lowry and published by . This book was released on 1982 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Nuclear Regulatory Commission supported an experimental program to study the mechanical properties of both unirradiated and irradiated fuel rod cladding. The program was designed to produce a mechanical property data base for use in developing modeling codes which could then be used to predict the performance of Zircaloy-4 clad fuel rods under various reactor loss-of-coolant accident (LOCA) conditions. Transient-heating burst tests were conducted at Argonne National Laboratory, Battelle Columbus Laboratories, and Oak Ridge National Laboratory as part of that program. A brief description of the testing methods, specimens, equipment, and procedures illustrates the similarities and differences in tests conducted at each laboratory. The data obtained from tests conducted in steam and utilizing test specimens with internal heaters or specimens containing alumina mandrels or pellets were compared for heating rates of 5, 28, and 55 C/sec. Both burst pressure and circumferential failure strain data versus burst temperature were plotted and compared in the range of 650 to 1250 C. It was found that testing methods, specimen oxidation layer, and irradiation effected the transient-heating burst test data.
Download or read book INIS Atomindex written by and published by . This book was released on 1988 with total page 902 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book High temperature Deformation and Rupture Behavior of Internally pressurized Zircaloy 4 Cladding in Vacuum and Steam Enivronments LOCA Conditions written by and published by . This book was released on 1977 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The high-temperature diametral expansion and rupture behavior of Zircaloy-4 fuel-cladding tubes have been investigated in vacuum and steam environments under transient-heating conditions that are of interest in hypothetical loss-of-coolant accident situations in light-water reactors. The effects of internal pressure, heating rate, axial constraint, and localized temperature nonuniformities in the cladding on the maximum circumferential strain have been determined for burst temperatures between approximately 650 and 1350°C.
Download or read book Reactor Materials written by and published by . This book was released on 1970 with total page 192 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 2001 with total page 952 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Reactor Core Materials written by and published by . This book was released on 1970 with total page 196 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Zirconium in the Nuclear Industry written by Leo F. P. Van Swam and published by ASTM International. This book was released on 1989 with total page 781 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Metals Abstracts written by and published by . This book was released on 1990-07 with total page 1466 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the International Topical Meeting on Light Water Reactor Fuel Performance written by and published by . This book was released on 1994 with total page 760 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Proceedings of the 1994 International Topical Meeting on Light Water Reactor Fuel Performance West Palm Beach Florida April 17 21 1994 written by and published by . This book was released on 1994 with total page 754 pages. Available in PDF, EPUB and Kindle. Book excerpt:
