Download or read book Radiation Creep and Swelling of Austenitic 16Cr 15Ni 3Mo Nb Steels Irradiated in the Reactor BOR 60 at 350 and 420 C written by VS. Neustroev and published by . This book was released on 1994 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radiation creep and swelling of 16Cr-15Ni-3Mo-Nb steels were studied after irradiation in the BOR-60 reactor at 350 and 420 C up to maximum fluence 11.9*1026 m-2 (E>0.1MeV), i.e. 60 dpa. Pressurized tubes were made of two steels with different carbon content (0.046 and 0.006 w. %). Swelling of the stress-free tubes depends on carbon content. Radiation creep rate depends only upon the stress level and the rate of swelling. Coefficients of swelling and creep interrelation are not sensitive to carbon content and irradiation temperature.
Download or read book Effects of Radiation on Materials written by Arvind S. Kumar and published by ASTM International. This book was released on 1994 with total page 1319 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Creep and Stress Affected Swelling in Austenitic Stainless Steel 16Cr 15Ni 3Mo Nb B Irradiated in the BN 350 Reactor written by AN. Vorobjev and published by . This book was released on 2000 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep and void swelling are important damage processes for stainless steels when subjected to neutron irradiation at elevated temperatures. To date, most published data of this type have been derived from steels prepared by various Western nations and Japan. This paper describes the results of an experiment involving irradiation of gas-pressurized tubes constructed from Russian niobium-stabilized austenitic steel EP-172 of type 16Cr-15Ni-3Mo-Nb doped with boron. The tubes were irradiated in the lowenrichment zone of the BN-350 fast reactor to three doses of 20, 45 and 60 dpa at temperatures in the range of 480-520°C.
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 Creep of Austenitic Steels Irradiated Up to High Damage Dose written by VK. Shamardin and published by . This book was released on 2000 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The irradiation-induced creep and swelling of annealed 16Cr-15Ni-3Mo-Nb stainless steels with different contents of carbon and boron in BOR-60 at 420°C have been investigated to exposures of 100 dpa. Swelling depends on carbon content and boron. The creep rate directly depends on stress and instantaneous swelling rate. The creep-swelling oupling coefficient of austenitic steels does not appear to be very sensitive to microaddition.
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 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 Metals Abstracts written by and published by . This book was released on 1994 with total page 1586 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Void Swelling and Microstructure of Austenitic Stainless Steels Irradiated in the BOR 60 Reactor written by and published by . This book was released on 2012 with total page 79 pages. Available in PDF, EPUB and Kindle. Book excerpt: As nuclear power plants age and neutron fluence increases, detrimental effects resulting from radiation damage have become an increasingly important issue for the operational safety and structural integrity of core internal components. In this study, irradiated specimens of reactor core internal components were characterized by transmission electron microscopy. The specimens had been irradiated to 5.5-45 dpa in the BOR-60 reactor at a dose rate close to 10-6 dpa/s and temperature of about 320°C. No voids were observed in the austenitic stainless steels and nickel alloys at all doses. Despite the possibility that fine voids below the TEM resolution limit may be present, it was clear that void swelling was insignificant in all examined alloys up to 45 dpa. Irradiated microstructures of the studied alloys were dominated by a high density of Frank loops. The mean size and density of the Frank loops varied from one material to another, but saturated with increasing dose above ~10 dpa. While no irradiation-induced precipitations were present below 24.5 dpa, fine precipitates were evident in several alloys at 45 dpa.
Download or read book Void Swelling and Microstructure of Austenitic Stainless Steels Irradiated in the BOR 60 Reactor written by Y. Chen and published by . This book was released on 2012 with total page 53 pages. Available in PDF, EPUB and Kindle. Book excerpt:
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 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 The Compositional Dependence of Irradiation Creep of Austenitic Alloys Irradiated in PFR at 420 degrees C written by and published by . This book was released on 1997 with total page 199 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep data are expensive and often difficult to obtain, especially when compared to swelling data. This requires that maximum use be made of available data sources in order to elucidate the parametric dependencies of irradiation creep for application to new alloys and to new environments such as those of proposed fusion environments. One previously untapped source of creep data is that of a joint U.S./U.K. experiment conducted in the Prototype Fast Reactor (PFR) in Dounreay, Scotland. In this experiment, five austenitic steels were irradiated in a variety of starting conditions. In particular, these steels spanned a large range (15-40%) of nickel contents, and contained strong variations in Mo, Ti, Al, and Nb. Some alloys were solution-strengthened and some were precipitation-strengthened. Several were cold-worked. These previously unanalyzed data show that at 420°C all austenitic steels have a creep compliance that is roughly independent of the composition of the steel at 2"1 x 10{sup -6}MPa{sup -1} dpa{sup -1}. The variation within this range may arise from the inability to completely separate the non-creep strains arising from precipitation reactions and the stress-enhancement of swelling. Each of these can be very sensitive to the composition and starting treatment of a steel.
Download or read book Irradiation Creep at Temperatures of 400 C and Below for Application to Near Term Fusion Devices written by ML. Grossbeck and published by . This book was released on 1999 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of 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 transmutation rate typical of a fusion device. Irradiation began in the Oak Ridge Research Reactor. After an atomic displacement level of 7.4 dpa was achieved, the specimens were moved to the High Flux Isotope Reactor for the remainder of the 19 dpa accumulated. Irradiation temperatures of 60, 200, 330, and 400°C were studied with internally pressurized tubes of type 316 stainless steel, PCA, HT 9, and a series of four laboratory heats of: Fe-13.5Cr-15Ni, Fe-13.5Cr-35Ni, Fe-13.5Cr-15Ni- 0.18Ti, and Fe-16Cr. At 330°C, irradiation creep was shown to be linear with fluence and stress. There was little or no effect of cold-work on creep under these conditions at all temperatures investigated. The HT9 demonstrated a large deviation from linearity at high stress levels, and a minimum in irradiation creep with increasing stress was observed in the Fe-Cr-Ni ternary alloys.
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 Comparison of Irradiation Creep and Swelling of an Austenitic Alloy Irradiated in FFTF and PFR written by FA. Garner and published by . This book was released on 1999 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Comparative irradiation of identically constructed creep tubes in the Fast Flux Test Facility (FFTF) and the Prototypic Fast Reactor (PFR) shows that differences in irradiation conditions arising from both reactor operation and the design of the irradiation vehicle can have a significant impact on the void swelling and irradiation creep of austenitic stainless steels. In spite of these differences, the derived creep coefficients fall within the range of previously observed values for 316 SS.
Download or read book Irradiation Creep in Austenitic Stainless Steels at 60 to 400 C with a Fusion Reactor Helium to Dpa Ratio written by M. P. Tanaka and published by . This book was released on 1990 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation creep was investigated in the alloys--prime candidate alloy (PCA), Japanese Fusion Energy Program (JPCA), and American Iron and Steel Institute (AISI) 316 (UNS S31600) stainless steel. Tubes pressurized to stress levels of 50 to 400 MPa were irradiated in the Oak Ridge Research Reactor (ORR) with the neutron spectrum tailored to achieve the fusion reactor helium:dpa value of 12 appm/dpa in AISI 316 stainless steel. Irradiation temperatures of 60, 330, and 400°C were investigated, and the irradiation produced 8 dpa and a maximum of about 100 appm helium. Irradiation creep rates of 2.2 to 14x10-4MPa-1dpa-1 were observed at 60°C. At 330 and 400°C irradiation creep rates of 1.3 to 3.5x10-4 were observed, similar to those found previously in similar experiments in the ORR. The low temperature irradiation creep was interpreted in terms of a new model for irradiation creep based on transient climb-enabled glide. The results are important in the design of experimental fusion reactors where temperatures below 100°C are being considered for the operation of high flux components.
