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Book The Microstructural Evolution and Swelling Behavior of Type 316 Stainless Steel Irradiated in HFIR

Download or read book The Microstructural Evolution and Swelling Behavior of Type 316 Stainless Steel Irradiated in HFIR written by S. Hamada and published by . This book was released on 1990 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Solution annealed (SA) and 20% cold worked (CW) Type 316 (UNS S 31600) stainless steels were irradiated in the high flux isotope reactor (HFIR) to 55 dpa and to 3445 appm helium at 300 to 500°C. The irradiated specimens were examined by transmission electron microscopy (TEM) to evaluate microstructural evolution. At irradiation temperatures of 400°C and below, there was very little difference in the microstructural and swelling behavior between SA and CW material. A high concentration of fine bubbles was uniformly dispersed in the matrix. Swelling was very low (

Book Effects of Radiation on Materials

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.

Book Swelling and Microstructural Evolution in 316 Stainless Steel Hexagonal Ducts Following Long Term Irradiation in EBR II

Download or read book Swelling and Microstructural Evolution in 316 Stainless Steel Hexagonal Ducts Following Long Term Irradiation in EBR II written by T. Yoshitake and published by . This book was released on 2001 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: Swelling behavior and microstructural evolution of 12% cold-worked 316 SS hexagonal ducts following irradiation in the outer rows of EBR-II is described. Immersion density measurements and transmission electron microscopy (TEM) examination were performed on a total of seven irradiation conditions. The samples were irradiated to temperatures between 375 and 430°C to doses between 23 and 51 dpa and at dose-rates ranging from 1.3 x 10-7 to 5.8 x 10-7 dpa/s. Dose-rates and temperatures approach conditions experienced by a variety of components in pressurized water reactors (PWR's) and those which may be present in future advanced reactors designs. TEM analysis was employed to elucidate the effect of radiation on the dislocation, void and precipitate structures as a function of irradiation conditions. A moderate dose-rate effect was observed for samples which were irradiated at dose-rates differing by a factor of two. Lower dose-rate samples contained voids of larger diameter and typically swelled more in the bulk. The dislocation and precipitate structure was not visibly influenced by a dose-rate decrease.

Book Swelling  Microstructural Development and Helium Effects in Type 316 Stainless Steel Irradiated in HFIR and EBR II

Download or read book Swelling Microstructural Development and Helium Effects in Type 316 Stainless Steel Irradiated in HFIR and EBR II written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This work examines the swelling and microstructural development of a single heat of 20%-cold-worked type 316 stainless steel irradiated to produce displacement damage and a high, continuous helium generation rate, in the High Flux Isotope Reactor (HFIR). Similar irradiation of the same heat of steel in the Experimental Breeder Reactor (EBR)-II is used as a base line for comparing displacement damage accompanying a very low continuous helium generation rate. At temperatures above and below the void swelling regime (approx. 350 to 625°C) swelling is greater in HFIR than in EBR-II. In the temprature range of 350 to 625°C, cavity formation, precipitation and dislocation recovery are both enhanced and accelerated in HFIR, often causing swelling at lower dose than in EBR-II. In HFIR, however, cavities appear to be bubbles rather than voids. They are about 10 times smaller and 20 to 50 times more numerous than voids in EBR-II. Thus, the swelling becomes greater in EBR-II than in HFIR for 20%-CW 316 in the void swelling temperature ranges as fluence increases. Such differences in swelling and microstructural behavior must be understood in order to anticipate the behavior of materials during fusion irradiation.

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1989 with total page 780 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Microstructural Evolution of Austenitic Stainless Steels Irradiated to 17 Dpa in Spectrally Tailored Experiment of the ORR and HFIR at 400 degrees C

Download or read book Microstructural Evolution of Austenitic Stainless Steels Irradiated to 17 Dpa in Spectrally Tailored Experiment of the ORR and HFIR at 400 degrees C written by and published by . This book was released on 1997 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The microstructural evolution of austenitic JPCA aged and solution annealed JPCA, 316R, C, K, and HP steels irradiated at 400°C in spectrally tailored experiments of the ORR and HFIR has been investigated. The helium generation rates were about 12-16 appm He/dpa on the average up to 17.3 dpa. The number densities and average diameters of dislocation loops in the steels have ranges of 3.3 x 1021 m−3 and 15.2-26.3 nm, respectively, except for HP steel for which they are 1.1 x 1023 m−3 and 8.0 nm. Precipitates are formed in all steels except for HP steel, and the number densities and average diameters have ranges of 5.2 x 102° - 7.7 x 1021 m−3 and 3.4- 19.3 nm, respectively. In the 216R, C, and K steels, the precipitates are also formed at grain boundaries, and the mean sizes of these are about 110, 50, and 50 nm, respectively. The number densities of cavities are about 1 x 1022 m−3 in all the steels. The swelling is low in the steels which form the precipitates.

Book Comparison of Swelling and Cavity Microstructural Development for Type 316 Stainless Steel Irradiated in EBR II and HFIR

Download or read book Comparison of Swelling and Cavity Microstructural Development for Type 316 Stainless Steel Irradiated in EBR II and HFIR written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Comparison of swelling and cavity microstructures for one heat of 20% cold-worked (CW) type 316 stainless steel (316) irradiated at 500 to 650°C in EBR-II (up to 75 dpa) and HFIR (up to 61 dpa) suggests that void growth and swelling are suppressed by the higher helium generation found in HFIR. Instead of voids, many small bubbles develop in the CW 316 in HFIR and resist conversion to voids. However, similar comparison of solution-annealed (SA) 316 irradiated in EBR-II and HFIR at 500 to 550°C leads to an opposite conclusion; void swelling is enhanced by helium in HFIR. Many more bubbles nucleate in SA 316 at low fluence in HFIR compared to EBR-II, but bimodel distributions and rapid coarsening eventually lead to high swelling due to high concentrations of matrix ands precipitate-associated voids in HFIR. A key to the swelling resistance of the CW 316 in HFIR appears to be the development of a sufficiently cavity-dominated sink system in the early stages of evolution.

Book ERDA Energy Research Abstracts

Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1985 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book ASTM Special Technical Publication

Download or read book ASTM Special Technical Publication written by and published by . This book was released on 1990 with total page 696 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Swelling of Microstructure of Neutron Irradiated Titanium Modified Type 316 Stainless Steel

Download or read book Swelling of Microstructure of Neutron Irradiated Titanium Modified Type 316 Stainless Steel written by Y. Carteret and published by . This book was released on 1985 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The analysis of the behavior of fuel pins irradiated in the same Rapsodie subassembly, shows that titanium has a marked beneficial effect on the swelling resistance of cold-worked Type 316 stainless steel in a wide temperature range. This effect is particularly visible at high temperature since cold-worked Type 316 titanium does not swell above 550°C up to a dose of 100 French displacements per atom (dpaF)(~74 dpa NRT).

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1994 with total page 982 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Swelling in Electron Irradiated Type 316 Stainless Steel

Download or read book Swelling in Electron Irradiated Type 316 Stainless Steel written by FA. Garner and published by . This book was released on 1975 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: To study void swelling behavior for clues regarding the anticipated performance of Type 316 stainless steel in fast reactor environments, two series of electron irradiation experiments were conducted. The first series of experiments were conducted on material which was prototypic of fast test reactor (FTR) steels in composition, but not microstructure. The results indicated that swelling values exceeding 100 percent could easily be obtained in annealed Type 316 and that cold rolling of this material could lead to an increase in the incubation fluence and a reduction in the subsequent swelling rate. The void volume fraction in both the annealed and cold-rolled specimens developed at a constant rate after the incubation period.

Book Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions

Download or read book Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions written by and published by . This book was released on 2015 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Extension of light water reactors' useful life will expose austenitic internal core components to irradiation damage levels beyond 100 displacements per atom (dpa), which will lead to profound microstructural evolution and consequent degradation of macroscopic properties. Microstructural evolution, including Frank loops, cavities, precipitates, and segregation at boundaries and the resultant radiation hardening in type 304 and 316 stainless steel (SS) variants, were studied in this work via experimental characterization and multiple simulation methods. Experimental data for up to 40 heats of type 304SS and 316SS variants irradiated in different reactors to 0.6-120 dpa at 275-375°C were either generated from this work or collected from literature reports. These experimental data were then combined with models of Frank loop and cavity evolution, computational thermodynamics and precipitation, and ab initio and rate theory integrated radiation-induced segregation models to provide insights into microstructural evolution and degradation at higher radiation doses.

Book Metals Abstracts

Download or read book Metals Abstracts written by and published by . This book was released on 1993 with total page 1044 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Swelling and Microstructure of HFIR Irradiated Austenitic Stainless Steels

Download or read book Swelling and Microstructure of HFIR Irradiated Austenitic Stainless Steels written by and published by . This book was released on 1980 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The swelling and microstructural information available from HFIR-CTRs-9-13 are summarized and compared for CW 316 and CW(316 + Ti). These experiments were irradiated to moderate fluences of about 8 to 16 dpa and 500 to 1000 at. ppM He at irradiation temperatures ranging from 285 to 670°C. These results are compared to higher fluence HFIR irradiation of CW 316 from HFIR-CTRs-2-8 irradiated at 375 to 680°C at fluences up to 61 dpa and 4200 at. ppM He. Both the high- and low-fluence cavity volume fraction swelling curves for CW 316 have a similar shape. The curves show a definite swelling minimum at 470 to 570°C that corresponds to the temperature of maximum precipitation. The swelling increases rather sharply with temperature at the higher and lower temperatures. The moderate fluence swelling levels are all below 0.5% .delta. V/V0.

Book INIS Atomindex

Download or read book INIS Atomindex written by and published by . This book was released on 1988 with total page 962 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Void Swelling and Microstructural Change in Neutron Irradiated Type 316 Stainless Steel

Download or read book Void Swelling and Microstructural Change in Neutron Irradiated Type 316 Stainless Steel written by M. Itoh and published by . This book was released on 1987 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Microstructural observations were made on cold-worked Type 316 stainless steel following fast neutron irradiation to a peak neutron fluence of 1.3 x 1027 n/m2 (E > 0.1 MeV) at temperatures from 400 to 620°C. The results show that nickel depletion in the matrix after neutron irradiation is related to the formation of phosphides and void swelling. Phosphorus in solution retards not only the recovery of dislocations but also the development of nickel- and silicon-rich phases, and this results in suppressing nickel depletion in the matrix and an extension of the transient regime in void swelling. Phosphides are formed during the transient regime at temperatures from 490 to 570°C. After phosphides are formed, retardation effects on both dislocation recovery and the formation of nickel- and silicon-rich phases are lost, and this leads to the onset of void swelling.