Download or read book The Ductile to Brittle Transition Behavior of Martensitic Steels Neutron Irradiated to 26 Dpa written by W-L Hu and published by . This book was released on 1987 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Charpy impact tests were conducted on specimens made of HT-9 and 9Cr-1Mo in various heat treatment conditions that were irradiated in EBR-II to 26 dpa at 390 to 500°C. The results are compared with previous results on specimens irradiated to 13 dpa. HT-9 base metal irradiated at low temperatures showed a small additional increase in ductile brittle transition temperature and a decrease in upper shelf energy from 13 to 26 dpa. No fluence effect was observed in 9Cr-1Mo base metal. The 9Cr-1Mo weldment showed degraded ductile-to-brittle transition temperature (DBTT) but improved upper shelf energy (USE) response compared to base metal, contrary to previous findings on HT-9. Significant differences were observed in HT-9 base metal between mill annealed material and normalized and tempered material. The highest DBTT for HT-9 alloys was 50°C higher than for the worst case in 9Cr-1Mo alloys. Fractography and hardness measurements were also obtained. Significant differences in fracture appearance were observed in different product forms, although no dependence on fluence was observed. Failure was controlled by the preirradiation microstructure.

Download or read book Influence of Radiation on Material Properties written by F. A. Garner and published by ASTM International. This book was released on 1987 with total page 806 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 1988 with total page 872 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Energy Research Abstracts written by and published by . This book was released on 1989 with total page 988 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Fracture Properties of Irradiated Alloys written by F. H. Huang and published by . This book was released on 1995 with total page 446 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 1995 with total page 636 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Recent Advances in Fracture written by Rao K. Mahidhara and published by Minerals, Metals, & Materials Society. This book was released on 1997 with total page 422 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work focuses on in-depth mechanics and materials aspects pertinent to the phenomena of ductile fracture in engineering materials. The 31 papers present recent advances that provide an increased level of understanding of many aspects of this type of fracture, including micromechanisms of fracture, sources of toughness, the effects of microstructure, hydrostatic pressure, temperature and strain rate.

Download or read book Evaluation of Ductile Brittle Transition Behavior of Helium implanted Reduced Activation 9Cr 2W Martensitic Steel by Small Punch Tests written by T. Morimura and published by . This book was released on 2000 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Helium implantation was performed by cyclotron with a beam of 36MeV-? particles at temperature below 429 K using a beam energy degrader to obtain homogeneous distribution of helium in a reduced activation 9Cr-2W martensitic steel up to a concentration of 120 at.ppm. The ductile-brittle transition temperature (DBTT) was evaluated by small punch (SP) tests in which the disk specimens of 3 mm diameter with 0.22 mm thickness were deformed by bulge mode. The shift in the DBTT (SP-?DBTT) and the increase in Vickers hardness (?Hv) caused by helium implantation were measured to be 26 K and 67 kg/mm2, respectively, which were estimated to be 65 K of standard CVN-?DBTT and 104 MPa of increase in the yield stress (??y) from empirical relationships between them. The enhancement of irradiation hardening by helium was never recognized and no change in the fracture mode at low temperatures was observed by the helium implantation. It is considered that the shift in the DBTT is mainly associated with irradiation hardening by displacement damage.

Download or read book INIS Atomindex written by and published by . This book was released on 1995 with total page 682 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Mechanical Properties of Four 7 9 Cr Reduced Activation Martensitic Steels After 2 5 Dpa 300 C Irradiation written by E. van Osch and published by . This book was released on 2000 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced Activation Ferritic/Martensitic alloys are being developed for application in future thermonuclear fusion reactors. The behavior of the reduced activation martensitic steel F82H-mod was compared with small amounts of related alloys JLF-1, JLF-1B and ORNL-9Cr2WVTa, following irradiation in the High Flux Reactor (HFR) in Petten. Tensile, KLST-type Charpy impact and CT fracture toughness mechanical properties specimens, were neutron irradiated to a dose level of 2-3 dpa at 300°C. Results of post irradiation tensile, miniaturized charpy impact, and static fracture toughness tests are presented and interpreted in terms of irradiation hardening and irradiation induced shift of ductile to brittle transition temperature (DBTT) and reduction of upper shelf energy (USE). The observed irradiation hardening (140 - 170 MPa at 300°C) is moderate, whereas the observed radiation induced shift in DBTT is approximately 150°C for KLST-type impact test specimens for F82H. Similar observations are made for the static fracture toughness tests. For JLF-1B the irradiation hardening is one third higher than for JLF-1, and shift in DBTT for JLF-1B is almost 70% larger than for JLF-1. The difference is attributed to the tenfold larger boron content prior to irradiation.

Download or read book Modeling of Helium Bubble Nucleation and Growth in Neutron Irradiated RAFM Steels written by Christian Dethloff and published by KIT Scientific Publishing. This book was released on 2014-05-22 with total page 194 pages. Available in PDF, EPUB and Kindle. Book excerpt: Reduced Activation Ferritic/Martensitic (RAFM) steels are first candidate structural materials in future fusion technology. In this work a physically based model using Rate Theory is developed to describe nucleation and growth of helium bubbles in neutron irradiated RAFM steels. Several modifications of the basic diffusion limited model are presented allowing a comprehensive view of clustering effects and their influence on expected helium bubble size distributions.

Download or read book ASM Handbook written by and published by . This book was released on 1990 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Technology written by and published by . This book was released on 1993 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Neutron Irradiation Effects on the Ductile brittle Transition of Ferritic written by and published by . This book was released on 1997 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Ferritic/martensitic steels such as the conventional 9Cr-1MoVNb (Fe-9Cr-1Mo-0.25V-0.06Nb-0.1C) and 12Cr-1MoVW (Fe-12Cr-1Mo-0.25V-0.5W-0.5Ni-0.2C) steels have been considered potential structural materials for future fusion power plants. The major obstacle to their use is embrittlement caused by neutron irradiation. Observations on this irradiation embrittlement will be reviewed. Below 425-450°C, neutron irradiation hardens the steels. Hardening reduces ductility, but the major effect is an increase in the ductile-brittle transition temperature (DBTT) and a decrease in the upper-shelf energy, as measured by a Charpy impact test. After irradiation, DBTT values can increase to well above room temperature, thus increasing the chances of brittle rather than ductile fracture. In addition to irradiation hardening, neutrons from the fusion reaction will produce large amounts of helium in the steels used to construct fusion power plant components. Tests to simulate the fusion environment indicate that helium can also affect the toughness. Steels are being developed for fusion applications that have a low DBTT prior to irradiation and then show only a small shift after irradiation. A martensitic 9Cr-2WVTa (nominally Fe-9Cr-2W-0.25V-0.07Ta-0.1C) steel had a much lower DBTT than the conventional 9Cr-1MoVNb steel prior to neutron irradiation and showed a much smaller increase in DBTT after irradiation. 27 refs., 5 figs., 1 tab.

Download or read book Neutron Irradiation Effects on the Ductile brittle Transition of Ferritic martensitic Steels written by and published by . This book was released on 1997 with total page 129 pages. Available in PDF, EPUB and Kindle. Book excerpt: Ferritic/martensitic steels such as the conventional 9Cr-1MoVNb (Fe-9Cr-1Mo-0.25V-0.06Nb-0.1C) and 12Cr-1MoVW (Fe-12Cr-1Mo-0.25V-0.5W-0.5Ni-0.2C) steels have been considered potential structural materials for future fusion power plants. The major obstacle to their use is embrittlement caused by neutron irradiation. Observations on this irradiation embrittlement is reviewed. Below 425-450°C, neutron irradiation hardens the steels. Hardening reduces ductility, but the major effect is an increase in the ductile-brittle transition temperature (DBTT) and a decrease in the upper-shelf energy, as measured by a Charpy impact test. After irradiation, DBTT values can increase to well above room temperature, thus increasing the chances of brittle rather than ductile fracture.