Download or read book Ductility and Hardening of Neutron Irradiated Fe Cr and Fe Cr Ni Steels written by N. Igata and published by . This book was released on 1992 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fe-Cr and Fe-Ni-Cr steels are candidate alloys for fusion reactor materials. For future design it is important to clarify the general rules of mechanical properties for those alloys irradiated at higher fluence and at higher temperatures. In this investigation, to find general rules for irradiation effects, twelve kinds of commercial Fe-Cr and Fe-Ni-Cr steels were irradiated in JMTR. The total flux was 6 x 1025n/m2, and the irradiation temperature was 743 to 848 K. Yield strength, tensile strength, and uniform ductility at room temperature were observed for all specimens before and after irradiation, and work-hardening exponents were obtained from stress-strain curves of those specimens. In all cases, uniform ductility was equal to the work-hardening exponent, there was a close relationship between strength and uniform ductility, and there was no anomalous behavior in these alloy series. Further study was made of Fe-9Cr-2Mo steel, which was irradiated to 3 x 1026 n/m2 at 673 to 923 K in EBR-II. Electron micrographs for controlled or irradiated specimens were used for the analysis of the change of strength by irradiation. The strength and uniform ductility was interpreted from microstructural aspects.
Download or read book Effects of Radiation on Materials written by Roger E. Stoller and published by ASTM International. This book was released on 1992 with total page 1315 pages. Available in PDF, EPUB and Kindle. Book excerpt: Symposium held in Nashville, Tennessee, June 1990. Almost two-thirds of these 91 papers are authored by researchers outside of the US (including information on research in the former USSR, Japan, and Europe). Topics include: current commercial power reactor systems; microstructural characterization
Download or read book Postirradiation Deformation Behavior in Ferritic Fe Cr Alloys written by and published by . This book was released on 1992 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: It has been demonstrated that fast-neutron irradiation produces significant hardening in simple Fe-(3-18)Cr binary alloys irradiated to about 35 dpa in the temperature range 365 to 420°C, whereas irradiation at 574°C produces hardening only for 15% or more chromium. The irradiation-induced changes in tensile properties are discussed in terms of changes in the power law work-hardening exponent. The work-hardening exponent of the lower chromium alloys decreased significantly after low-temperature irradiation ((less-than or equal to) 420°C) but increased after irradiation at 574°C. The higher chromium alloys failed either in cleavage or in a mixed ductile/brittle fashion. Deformation microstructures are presented to support the tensile behavior.
Download or read book Postirradiation Deformation Behavior in Ferritic Fe Cr Alloys written by PL. Gardner and published by . This book was released on 1994 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: It has been demonstrated that fast neutron irradiation produces significant hardening in simple Fe-(3-18)Cr binary alloys irradiated to about 35 dpa in the temperature range 365 to 420°C, whereas irradiation at 574°C produces hardening only for 15% or more chromium. The irradiation-induced changes in tensile properties are discussed in terms of changes in the power law work hardening exponent. The work hardening exponent of the lower chromium alloys decreased significantly after low temperature irradiation (
Download or read book Effects of Radiation on Materials written by and published by . This book was released on 1996 with total page 1192 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Effects of Nickel on Microstructural Development and Microchemical Changes in Neutron Irradiated Fe Cr Mn Based Steels written by H. Takahashi and published by . This book was released on 1992 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: Microstructural changes and solute segregation in austenitic Fe-Cr-Mn-Ni alloys have been studied after neutron irradiation to 25 dpa (maximum) in FFTF/MOTA. Voids were nucleated in all of the specimens in the temperature range of 420 to 650°C, and a swelling peak was observed to form at 550°C. The void suppression effect of nickel additions did not occur in these alloys. Precipitates were formed in the matrix and/or on grain boundaries and were mostly identified as M23C6. The composition in the grain boundary area changed, and the chromium (Cr) concentration near the precipitates became higher. On the other hand, manganese and chromium were depleted, and nickel was enriched in the grain boundary area, but without precipitation. Other phases such as ferrite and sigma could not be recognized. Thus, it was revealed that the addition of nickel to Fe-Cr-Mn alloy stabilizes the austenite even in the grain boundary area where segregation is marked.
Download or read book Microstructure Evolution in Proton irradiated Austenitic Fe Cr Ni Alloys Under LWR Core Conditions written by Jian Gan and published by . This book was released on 1999 with total page 710 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Microstructures in Neutron Irradiated Fe Cr Ni P Ti Model Austenitic Alloys Doped with 10B written by T. Muroga and published by . This book was released on 1999 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fe-16Cr-17Ni ternary alloy and those with addition of 0.024P, 0.1P and 0.1P+0.25Ti were irradiated with fast neutrons in FFTF/MOTA at 793 K and 874 K to 33 dpa and 60 dpa. For the purpose of investigating helium production effect, two levels of 10B were doped for each alloy. The microstructures and their relation with tensile properties were examined. The yield stress change was correlated with the density of phosphide precipitates.
Download or read book Improvement of Post Irradiation Ductility of V Ti Cr Si Type Alloys Neutron Irradiated Around 400 C written by M. Satou and published by . This book was released on 2000 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Mechanical properties after neutron irradiation at temperatures around 400°C of the V-Ti-Cr-Si type alloys were reported. Neutron irradiation was carried out at temperatures 374 °C and 406 °C with fluence of about 7 and 50 dpa, respectively. Tensile tests were conducted using miniaturized specimens at ambient temperature and irradiation temperature. Uniform elongation of the alloy V-5Ti-5Cr-1Si-1Al-1Y (nominal weight percentage) was maintained at about 4.2 and 5.9% after irradiation and testing at 374 and 406 °C, respectively. Increases in yield stress were 240 MPa and 160 MPa, respectively. Although the irradiation hardening was large, apparently smaller than that of V-Ti-Cr type alloys without Si, Al and Y additions, it was possible that the additional elements reduced the concentration of interstitial impurities in solution, which caused high irradiation hardening. It was found that a small addition of Si, Al and Y showed possible improvement in the ductility at lower temperature irradiation of vanadium alloys.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 700 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 1978 with total page 548 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Radiation Tolerance of Neutron Irradiated Model Fe Cr Al Alloys written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The Fe Cr Al alloy system has the potential to form an important class of enhanced accident-tolerant cladding materials in the nuclear power industry owing to the alloy system's higher oxidation resistance in high-temperature steam environments compared with traditional zirconium-based alloys. However, radiation tolerance of Fe Cr Al alloys has not been fully established. In this study, a series of Fe Cr Al alloys with 10 18 wt % Cr and 2.9 4.9 wt % Al were neutron irradiated at 382 C to 1.8 dpa to investigate the irradiation-induced microstructural and mechanical property evolution as a function of alloy composition. Dislocation loops with Burgers vector of a/2 111 and a 100 were detected and quantified. Results indicate precipitation of Cr-rich is primarily dependent on the bulk chromium composition. Mechanical testing of sub-size-irradiated tensile specimens indicates the hardening response seen after irradiation is dependent on the bulk chromium composition. A structure property relationship was developed; it indicated that the change in yield strength after irradiation is caused by the formation of these radiation-induced defects and is dominated by the large number density of Cr-rich precipitates at sufficiently high chromium contents after irradiation.
Download or read book Structural Alloys for Nuclear Energy Applications written by Robert Odette and published by Newnes. This book was released on 2019-08-15 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors' unique personal insight from decades of frontline research, engineering and management. - Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. - Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. - Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
Download or read book Zirconium in the Nuclear Industry written by Craig M. Eucken and published by ASTM International. This book was released on 1991 with total page 794 pages. Available in PDF, EPUB and Kindle. Book excerpt: The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr
Download or read book Microstructural Characterization of Irradiated Fe Cu Ni P Model Steels written by and published by . This book was released on 1987 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: The microstructure of Fe-Cu-Ni-P model pressure vessel steels after neutron irradiation and thermal aging has been characterized by atom probe field-ion microscopy and augmented by transmission electron microscopy. High densities of small, roughly spherical or disc shaped copper clusters/precipitates were observed in the neutron irradiated alloys that contained copper. Small spherical phosphorus clusters were observed in the irradiated copper-free alloys, and copper phosphides were observed in a high phosphorus Fe-Cu-Ni-P alloy. None of these clusters/precipitates were observed in the thermally aged materials. The increases in the tensile and yield strengths that were observed after neutron irradiation resulted from these clusters and other lattice defects.
Download or read book Postirradiation Strength and Deformation of Ferritic Fe Cr Binary Alloys written by DS. Gelles and published by . This book was released on 1992 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Six binary Fe-Cr alloys with chromium levels ranging from 3 to 18% were tensile tested at room temperature following irradiation at 365, 403, and 574°C to doses of 7.4, 37.7, and 34.3 dpa, respectively. Irradiation at 365 and 403°C produced significant strengthening at all chromium levels, with concurrent reductions in ductility. Strength levels were insensitive to composition, irradiation temperature, or neutron exposure. Irradiation at 574°C produced strength increases at only the two highest chromium levels. The results are attributed to dislocation loop and void development at 365 and 403°C, and phase instability at 574°C. No evidence for channel fracture was found.
Download or read book Monthly Accession List written by Radiation Effects Information Center (Columbus, Ohio). and published by . This book was released on 1968 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:
