Download or read book IRRADIATION CREEP AND MECHANICAL PROPERTIES OF TWO FERRITIC MARTENSITIC STEELS IRRADIATED IN THE BN 350 FAST REACTOR written by and published by . This book was released on 2002 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Russian ferritic/martensitic steels EP-450 and EP-823 were irradiated to 20-60 dpa in the BN-350 fast reactor in the form of pressurized creep tubes and small rings used for mechanical property tests. Data derived from these steels serves to enhance our understanding of the general behavior of this class of steels. It appears that these steels exhibit behavior that is very consistent with that of Western steels. Swelling is relatively low at high neutron exposure and confined to temperatures less then 420 degrees C, but may be camouflaged somewhat by precipitation-related densification. The irradiation creep studies confirm that the creep compliance of F/M steels is about one-half that of austenitic steels, and that the loss of strength at test temperatures above 500 degrees C is a problem generic to all F/M steels. This conclusion is supported by post-irradiation measurement of short-term mechanical properties. At temperatures below 500 degrees C both steels retain their high strength (yield stress 0.2=550-600 MPa), but at higher test temperatures a sharp decrease of strength properties occurs. However, the irradiated steels still retain high post-irradiation ductility at test temperatures in the range of 20-700 degrees C.

Download or read book IRRADIATION CREEP AND SWELLING OF RUSSIAN FERRITIC MARTENSITIC STEELS IRRADIATED TO VERY HIGH EXPOSURES IN THE BN 350 FAST REACTOR AT 305 335 DEGREES C written by Francis A. Garner and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Russian ferritic martensitic (F(slash)M) steels EP(dash)450, EP(dash)852 and EP(dash)823 were irradiated in the BN(dash)350 fast reactor in the form of gas-pressurized creep tubes. The first steel is used in Russia for hexagonal wrappers in fast reactors. The other steels were developed for compatibility with Pb(dash)Bi coolants and serve to enhance our understanding of the general behavior of this class of steels. In an earlier paper we published data on irradiation creep of EP(dash)450 and EP(dash) 823 at temperatures between 390 and 520 degrees C, with dpa levels ranging from 20 to 60 dpa. In the current paper new data on the irradiation creep and swelling of EP(dash)450 and EP(dash)852 at temperatures between 305 and 335 degrees C and doses ranging from 61 to 89 dpa are presented. Where comparisons are possible, it appears that these steels exhibit behavior that is very consistent with that of Western steels. Swelling is relatively low at high neutron exposure and confined to temperatures less then 420 degrees C, but may be camouflaged somewhat by precipitation related densification. These irradiation creep studies confirm that the creep compliance of F(slash)M steels is about one half that of austenitic steels.

Download or read book Irradiation Creep and Swelling of Russian Ferritic Martensitic Steels Irradiated to Very High Exposures in the BN 350 Fast Reactor at 305 335 C written by SV. Shulepin and published by . This book was released on 2004 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Russian ferritic/martensitic (F/M) steels EP-450, EP-852, and EP-823 were irradiated in the BN-350 fast reactor in the form of gas-pressurized creep tubes. The first steel is used in Russia for hexagonal wrappers in fast reactors. The other steels were developed for compatibility with Pb-Bi coolants and serve to enhance our understanding of the general behavior of this class of steels.

Download or read book Effects of Radiation on Materials written by Martin L. Grossbeck and published by ASTM International. This book was released on 2004 with total page 767 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation Effects in Structural Alloys for Thermal and Fast Reactors written by and published by ASTM International. This book was released on with total page 437 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nickel Doped Ferritic Martensitic Steels for Fusion Reactor Irradiation Studies written by RL. Klueh and published by . This book was released on 1982 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: When an alloy containing nickel is irradiated in a mixed-spectrum reactor, helium is produced in the lattice by the transmutation of 58Ni by thermal neutrons. Nickel doping of two ferritic (martensitic) steels is being used to determine the effect of simultaneously produced helium and displacement damage (produced by the fast neutrons in the spectrum) on the mechanical properties of these steels, which are structural candidates for fusion reactor applications. Heats of 9 Cr-1 MoVNb and 12 Cr-1 MoVW with up to 2% Ni have been prepared. Tempering studies were conducted to determine the effect of nickel on the basic alloys and to identify the appropriate tempering temperature and time. Tensile specimens of the steels were irradiated in the High Flux Isotope Reactor to displacement damage levels of up to 9.3 dpa and helium concentrations of up to 82 at. ppm. Tensile studies at room temperature and 300°C on the 9 Cr-1 MoVNb steels indicated that the irradiation led to increased strength and decreased ductility compared to the steels in the unirradiated condition. It was concluded that the hardening resulted from the displacement damage and was not affected by the transmutation helium. The results were similar to tensile properties previously obtained for nickel-doped 12 Cr-1 MoVW steel irradiated under similar conditions.

Download or read book Effects of Radiation on Materials written by N. H. Packan and published by ASTM International. This book was released on 1990 with total page 679 pages. Available in PDF, EPUB and Kindle. Book excerpt: Annotation Effects of Radiation on Materials: Fourteenth International Symposium was presented at Andover, MA, June 1988. The symposium was sponsored by ASTM Committee E-10 on Nuclear Technology and Applications. The papers from the first three days of the symposium appear in the two volumes of this publication. Volume I encompasses radiation damage- induced microstructures; point defect, solute, and gas atom effects; atomic-level measurement techniques; and applications of theory. Volume II includes mechanical behavior, all papers dealing with pressure-vessel steels, breeder reactor components, dosimetry, and nuclear fuels. The fourth day of the symposium was devoted to the single topic of reduced-activation materials (see TK9204). The two volumes are separately sold at $127 and $128 respectively; each is independently indexed. Annotation copyrighted by Book News, Inc., Portland, OR.

Download or read book Post Irradiation Tensile Behavior and Residual Activity of Several Ferritic Martensitic and Austenitic Steels Irradiated in Osiris Reactor at 325 C Up to 9 Dpa written by F. Rozenblum and published by . This book was released on 2005 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: An experimental irradiation, named "Alexandre," has been carried out in the Osiris experimental reactor to perform a generic study on the mechanical behavior after irradiation at 325°C of different kinds of steels suitable for use as irradiated components in a nuclear reactor [1]. The irradiated steels were austenitic stainless, martensitic (conventional and reduced activation), and ferritic-martensitic Oxide Dispersion Strengthened steels in various initial metallurgical conditions. The final dose was 9 dpa, which represents nearly a "saturation" dose for the hardening/embrittlement of both austenitic and martensitic steels. At this dose, the Yield Strength and the Ultimate Tensile Strengths are almost equal, and strong localization of the plastic deformation is often observed.

Download or read book Effects of Radiation on Materials written by Todd R. Allen and published by ASTM International. This book was released on 2006 with total page 411 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation Effects on the Microstructure on Properties of Metals written by ASTM International Symposium on Effects of Radiation on Structural Materials and published by ASTM International. This book was released on 1976 with total page 502 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Radiation Effects in Breeder Reactor Structural Materials written by Melvin L. Bleiberg and published by . This book was released on 1977 with total page 986 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Microstructural Evolution of Ferritic martensitic Steels Under Heavy Ion Irradiation written by Cem Topbasi and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Ferritic-martensitic steels are primary candidate materials for fuel cladding and internal applications in the Sodium Fast Reactor, as well as first-wall and blanket materials in future fusion concepts because of their favorable mechanical properties and resistance to radiation damage. Since microstructure evolution under irradiation is amongst the key issues for these materials in these applications, developing a fundamental understanding of the irradiation-induced microstructure in these alloys is crucial in modeling and designing new alloys with improved properties.The goal of this project was to investigate the evolution of microstructure of two commercial ferritic-martensitic steels, NF616 and HCM12A, under heavy ion irradiation at a broad temperature range. An in situ heavy ion irradiation technique was used to create irradiation damage in the alloy; while it was being examined in a transmission electron microscope. Electron-transparent samples of NF616 and HCM12A were irradiated in situ at the Intermediate Voltage Electron Microscope (IVEM) at Argonne National Laboratory with 1 MeV Kr ions to ~10 dpa at temperatures ranging from 20 to 773 K. The microstructure evolution of NF616 and HCM12A was followed in situ by systematically recording micrographs and diffraction patterns as well as capturing videos during irradiation.In these irradiations, there was a period during which no changes are visible in the microstructure. After a threshold dose (~0.1 dpa between 20 and 573 K, and ~2.5 dpa at 673 K) black dots started to become visible under the ion beam. These black dots appeared suddenly (from one frame to the next) and are thought to be small defect clusters (2-5 nm in diameter), possibly small dislocation loops with Burgers vectors of either 1/2111 or 100.The overall density of these defect clusters increased with dose and saturated around 6 dpa. At saturation, a steady-state is reached in which defects are eliminated and created at the same rates so that the defect density is constant. After saturation, defects constantly appeared and disappeared in a time that is shorter than the time in between frames (normally 34 ms). The average diameter and size distribution of the irradiation-induced defect clusters did not vary with dose during a single irradiation in the temperature range of 50 to 573 K in NF616, and 20 to 673 K in HCM12A. At 673 K, the defects in NF616 grew and coalesced under irradiation which led to larger average defect sizes and low defect density. At high doses extended defect structures in NF616 formed as short segments aligned along 100 directions. At 773 K, the frequency of defect formation per unit area was the lowest amongst all irradiations and all the visible defect clusters that formed eventually faded out gradually (in ~28 seconds) leading to no net defect accumulation in NF616 even at the highest irradiation dose of 10 dpa.Under irradiation, a significant fraction of these defect clusters exhibited sudden one-dimensional jumps (over ~5nm) between 20 and 573 K, that is, some defect clusters move "or jump" along 211 directions which is consistent with the expected Burgers vector direction of (111). Interestingly, at 673 and 773 K, defects in NF616 and HCM12A did not exhibit the sudden jumps and jerks that were frequently observed during lower temperature irradiations. No resolvable loops, voids or precipitates were formed in NF616 and HCM12A. Furthermore, no significant interaction of the irradiation induced defects with the foil surface, pre-existing dislocation network or grain boundaries was observed between 20 and 773 K.A simplified rate theory model was developed to describe the initial defect formation processes. The model is based on the reactions between intra-cascade clusters driven by the one-dimensional movement of sub-visible interstitial clusters in their glide cylinder under irradiation after detrapping from interstitial and substitutional solute atoms by cascade impact. Multiple cascade impacts on previously existing clusters allow them to gather clusters during their glide, leading to the formation of TEM-visible (~2 nm) defects. The low dose defect density approximated by model is in good agreement with the experimental results. In addition, the model rationalizes the threshold dose before which no visible defect clusters were formed.

Download or read book Irradiation Creep and Stress enhanced Swelling of Fe 16Cr 15Ni Nb Austenitic Stainless Steel in BN 350 written by and published by . This book was released on 1997 with total page 200 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep and void swelling will be important damage processes for stainless steels when subjected to fusion neutron irradiation at elevated temperatures. The absence of an irradiation device with fusion-relevant neutron spectra requires that data on these processes be collected in surrogate devices such as fast reactors. This paper presents the response of an annealed austenitic steel when exposed to 60 dpa at 480°C and to 20 dpa at 520°C. This material was irradiated as thin-walled argon-pressurized tubes in the BN-350 reactor located in Kazakhstan. These tubes were irradiated at hoop stresses ranging from 0 to 200 MPa. After irradiation both destructive and non-destructive examination was conducted.

Download or read book Irradiation Creep in Austenitic and Ferritic Steels Irradiated in a Tailored Neutron Spectrum to Induce Fusion Reactor Levels of Helium written by and published by . This book was released on 1996 with total page 2 pages. Available in PDF, EPUB and Kindle. Book excerpt: Six austenitic stainless steels and two ferritic alloys were irradiated sequentially in two research reactors where the neutron spectrum was tailored to produce a He production rate typical of a fusion device. Irradiation began in the Oak Ridge Research Reactor where an atomic displacement level of 7.4 dpa was achieved and was then transferred to the High Flux Isotope Reactor for the remainder of the irradiation to a total displacement level of 19 dpa. Temperatures of 60 and 330°C are reported on. At 330°C irradiation creep was found to be linear in stress and fluence with rates in the range of 1.7 - 5.5 x 10−4% MPa−1 dpa−1. Annealed and cold-worked materials exhibited similar creep rates. There is some indication that austenitic alloys with TiC or TiO precipitates had a slightly higher irradiation creep rate than those without. The ferritic alloys HT-9 and Fe-16Cr had irradiatoin creep rates about 0.5 x 10−4% MPa−1 dpa−1. No meaningful data could be obtained from the tubes irradiated at 60°C because of damage to the tubes.

Download or read book Fast Reactor Core and Fuel Structural Behavior written by British Nuclear Energy Society and published by Thomas Telford Publishing. This book was released on 1990 with total page 340 pages. Available in PDF, EPUB and Kindle. Book excerpt: Analysis and exchange of information about the structural behaviour of fast reactor cores and core components has never been more important to the nuclear energy industry. This book covers the whole range of the design, development, safety and in-service aspects of core and fuel structural performance.

Download or read book Heat to heat Variability of Irradiation Creep and Swelling of HT9 Irradiated to High Neutron Fluence at 400 600 degrees C written by and published by . This book was released on 1996 with total page 189 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep data on ferritic/martensitic steels are difficult and expensive to obtain, and are not available for fusion-relevant neutron spectra and displacement rates. Therefore, an extensive creep data rescue and analysis effort is in progress to characterize irradiation creep of ferritic/martensitic alloys in other reactors and to develop a methodology for applying it to fusion applications. In the current study, four tube sets constructed from three nominally similar heats of HT9 subjected to one of two heat treatments were constructed as helium-pressurized creep tubes and irradiated in FFTF-MOTA at four temperatures between 400 and 600°C. Each of the four heats exhibited a different stress-free swelling behavior at 400°C, with the creep rate following the swelling according to the familiar B{sub o} + DS creep law. No stress-free swelling was observed at the other three irradiation temperatures. Using a stress exponent of n = 1.0 as the defining criterion, {open_quotes}classic{close_quotes} irradiation creep was found at all temperatures, but, only over limited stress ranges that decreased with increasing temperature. The creep coefficient B{sub o} is a little lower (≈50%) than that observed for austenitic steel, but the swelling-creep coupling coefficient D is comparable to that of austenitic steels. Primary transient creep behavior was also observed at all temperatures except 400°C, and thermal creep behavior was found to dominate the deformation at high stress levels at 550 and 600°C.

Download or read book Dimensional Stability and Mechanical Behaviour of Irradiated Metals and Alloys written by British Nuclear Energy Society and published by . This book was released on 1983 with total page 228 pages. Available in PDF, EPUB and Kindle. Book excerpt: Sessions at this conference were entitled: 'Micro-structural Development and Void Swelling', 'In-reactor Creep', 'High Temperature Mechanical Properties', 'Thermal Reactor Materials' and 'Design and Performance of Reactor Components and Structures'.