Download or read book Comparison of Transition Temperature Shifts Between Static Fracture Toughness and Charpy v Impact Properties Due to Irradiation and Post Irradiation Annealing for Japanese A533B 1 Steels written by M. Suzuki and published by . This book was released on 2001 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: It is assumed in the integrity analysis of reactor pressure vessel (RPV) that the irradiation-induced shift of fracture toughness in the ductile-brittle transition region is the same as the Charpy transition temperature shift. To confirm this assumption, both shifts are compared using irradiated and post-irradiation annealed RPV steels made by Japanese manufacturers. Five ASTM A533B class 1 plates having high- and low-level impurities, which correspond to first generation and modern Japanese reactors are used in this study. Neutron irradiation of precracked Charpy-v (PCCv) specimens as well as standard Charpy-v specimens was carried out at the Japan Materials Testing Reactor (JMTR). The values of fast neutron fluence for this study are 2 to 13x1019 (n/cm2, E>1MeV) considering typical fluence values at the EOL and extended operation of Japanese PWRs. The irradiation temperature was controlled within the range of 290±10°C. Thermal annealing treatments at 350°C and 450°C for 100 hours were performed for irradiated PCCv and Charpy-v specimens. The master curve approach according to ASTM Test Method for Determination of Reference Temperature, T0, for Ferritic Steels in the Transition Range (E1921) was applied using PCCv specimens. The irradiation-induced shifts of the reference temperature, ?T0, obtained in this study were spread in the range of 10 to 200°C. The annealing recoveries of the reference temperature were compared with those of the Charpy transition temperature. Although large scatter was seen in the relation between ?T0 values and Charpy 41J shifts, both shifts were almost the same in the average.

Download or read book Effects of Radiation on Materials written by Stan T. Rosinski and published by ASTM International. This book was released on 2001 with total page 879 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 Proceedings of the ASME Pressure Vessels and Piping Conference 2006 Operations applications and components written by and published by . This book was released on 2007 with total page 730 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book RPV Integrity and Fracture Mechanics written by Dominique Moinereau and published by . This book was released on 2004 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book JSME International Journal written by and published by . This book was released on 2004 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Annual Book of ASTM Standards written by ASTM International and published by . This book was released on 2004 with total page 1268 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Correlation Between Microhardness Tensile Properties and Notch Ductility of Irradiated Ferritic Steels written by Holland, JR. and published by . This book was released on 1981 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: The work demonstrates that changes in Charpy V-notch impact properties can be monitored by microhardness measurements for radiation-embrittled ferritic steels in the transition region. A qualitative basis for understanding this relationship is developed from extension of existing models for lower-shelf fracture toughness and analysis of the shifts in the ductile-to-brittle transition temperature with changes in the yield strength. Microhardness is shown to correlate with the yield stress of the irradiated ferritic materials described in this report. A comparison of Charpy energy and yield stress data suggests that, for the purposes of this analysis, the fracture stress is insensitive to both irradiation and annealing in the transition region.

Download or read book Fracture Toughness Thermo Electric Power and Atom Probe Investigations of JRQ Steel in I IA IAR and IARA Conditions written by Ph Tipping and published by . This book was released on 2005 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: The International Atomic Energy Agency has sponsored a number of studies involving a specific plate of A533 grade B class 1 steel designated heat JRQ. In this cooperative study between the Paul Scherrer Institute (PSI) and the Heavy-Section Steel Irradiation Program of Oak Ridge National Laboratory (ORNL), groups of Charpy impact, tensile, and precracked Charpy specimens of the JRQ plate were irradiated by PSI to four different fast neutron fluences [from 0.39 to 5.0 × 1023 n/m2 (>1 MeV)] in a test reactor. Additional specimens were given a post-irradiation thermal annealing treatment at 460°C for 18 h when 50 % of the target fluence was reached, followed by reirradiation to the same target fluences for the four groups of irradiated specimens. Additionally, ORNL thermally annealed some of the reirradiated specimens, as well as some of those in the irradiated only condition. Charpy impact, tensile, fracture toughness, and hardness tests have been performed to evaluate material response in the various conditions and to compare with the unirradiated material. Additionally, thermo-electric power experiments have been conducted by PSI, while atom probe tomography evaluations have been conducted by ORNL. Except at the highest fluence, the results show that the material given an intermediate annealing treatment exhibited irradiation-induced transition temperature shifts about the same as those that were only irradiated. However, the upper-shelf energies were generally higher and the yield strengths were generally lower for the reirradiated groups. The intermediate thermal annealing resulted in less reirradiation embrittlement of fracture toughness than Charpy impact toughness, while annealing after reirradiation resulted in significant increases in Charpy upper-shelf energy above that in the unirradiated condition. Irradiation-induced and IAR Charpy impact transition temperature shifts exhibit a nearly linear correlation with Seebeck coefficient in the I and IAR conditions. ORNL has also sent additional specimens from I, IA, IAR, and IARA test of JRQ for additional TEP testing. After irradiation, a high number density of ultrafine Cu-, Mn-, Ni-, Si-, and P-enriched precipitates were observed by atom probe tomography. Phosphorus segregation to dislocations was also observed. A significantly lower number density of larger Cu-, Mn-, and Ni- enriched precipitates was observed after the second annealing treatment.

Download or read book Neutron Irradiation Embrittlement of Reactor Pressure Vessel Steels written by Lendell E. Steele and published by . This book was released on 1975 with total page 252 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Mechanical Properties of Irradiated Plain Carbon and Alloy Steels written by Richard E. Schreiber and published by . This book was released on 1961 with total page 88 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 1256 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fracture Toughness Characterization of Irradiated F82H in the Transition Region written by H. Tanigawa and published by . This book was released on 2004 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: The ferritic-martensitic steel F82H is a primary candidate low-activation material for fusion applications, and it is being investigated in the joint U.S. Department of Energy-Japan Atomic Energy Research Institute (U.S. DOE-JAERI) collaboration program. As part of this program, two capsules containing a variety of specimen designs were irradiated at two different temperatures in the Oak Ridge National Laboratory (ORNL) High Flux Isotope Reactor (HFIR). The bottom and top parts of these capsules were loaded with disk-shaped compact tension [DC(T)] specimens that were used for fracture toughness characterization. This small (12.5-mm-diam and of 4.6-mm-thick) DC(T) specimen was developed at ORNL for testing irradiated materials. Six specimens were irradiated in each "low-"and "high-" irradiation temperature capsule up to ~3.8 dpa. Irradiation temperatures were measured by thermocouples. In the low-temperature capsule, three specimens were irradiated at an average temperature of 261°C and another three at 240°C; temperature variation during irradiation was within ±19°C for a given specimen. In the high-temperature capsule, all six specimens were irradiated at an average temperature of 377°C in the bottom part of the capsule; temperature variation during irradiation was within ±30°C for a given specimen. All irradiated specimens failed by cleavage instability. From these data, fracture toughness transition temperatures were evaluated for irradiated F82H steel and compared to unirradiated values. Specimens irradiated at the higher temperature exhibited a relatively modest shift of the fracture toughness transition temperature of ~57°C. However, the shift of fracture toughness transition temperature of specimens irradiated at 250°C was much larger, ~191°C. These results are compared with available tensile and impact Charpy data for this material.

Download or read book Metals Abstracts written by and published by . This book was released on 1996 with total page 762 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Effect of Loading Rate Upon Irradiation Embrittlement Measured by Fracture Mechanical Properties written by R. Ahlstrand and published by . This book was released on 1994 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent investigations have shown that the Charpy-V test is an unreliable indicator of the true irradiation embrittlement. This has increased the need for a direct measurement of the fracture toughness. In the case of surveillance testing, where the specimen size is typically small, especially two types of tests are attractive, static testing based on the J-integral and dynamic testing performed by the instrumented impact hammer. Many factors speak in favor for the dynamic test. However, it is not clear whether the irradiation embrittlement is depicted similarly by static and dynamic tests. In this work the the effect of loading rate upon irradiation embrittlement measured by fracture mechanical properties is investigated. It is shown that the shift in the fracture toughness transition temperature is smaller for dynamic loading than for static loading and a theoretical explanation for the effect is proposed.

Download or read book The Relationship Between Fracture Toughness and Charpy Impact Transition Temperatures in Mild Steel written by D. A. Curry and published by . This book was released on 1979 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fracture Toughness and Atom Probe Characterization of a Highly Embrittled RPV Weld written by MA. Sokolov and published by . This book was released on 2004 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Heavy-Section Steel Irradiation Program at Oak Ridge National Laboratory (ORNL) includes a task to investigate the shape of the fracture toughness master curve for reactor pressure vessel steel highly embrittled as a consequence of irradiation exposure. A radiation-sensitive reactor pressure vessel (RPV) weld with intentionally enhanced copper content, designated KS-01, is characterized in terms of static initiation (KIc, KJc) and Charpy impact toughness in the unirradiated and irradiated conditions. The objective of this project is to investigate the ability of highly embrittled material to maintain the shape of the unirradiated transition fracture toughness curve, as well as to examine the ability of the Charpy 41-J shift to predict the fracture toughness shift at such a high level of embrittlement. Irradiation of this weld was performed at the University of Michigan Ford Reactor. Specimens of KS-01 weld were irradiated to about 0.74 x 1019 neutron/cm2 at 288°C. Irradiation resulted in Charpy ductile-to-brittle transition temperature (DBTT) shift of 169°C. It was anticipated that this shift would result in a fracture toughness transition temperature (at 100 MPa?m) in the irradiated condition near or slightly above the pressurized thermal shock screening criterion for weld metals, ToPTS = 129°C. The fracture toughness characterization of KS-01 weld in the unirradiated and irradiated conditions was mainly performed by testing 1T C(T), although some 0.5T C(T) and precracked Charpy specimens were used in this study. The master curve analysis showed that this material exhibited shift of reference fracture toughness transition temperature, To, of 165°C as result of radiation, which is in remarkable agreement with Charpy DBTT shift. The absolute value of To in the irradiated condition was determined to be equal to 139°C. This weld exhibited a low ductile initiation toughness (JQ) after irradiation. It left a relatively narrow temperature window to examine the shape of the transition region. Irradiated median fracture toughness values up to 148 MPa?m follow the master curve shape. However, low toughness brittle fractures occurred at temperatures further above To (To + 61°C) than expected with a leveling of the KJc data from the master curve shape. The microstructure of the weld was characterized with the ORNL's energy-compensated optical position-sensitive atom probe. Atom probe tomography revealed a high number density (~3 x 1024m-3) of Cu-, Mn-, Ni-, Si-, and P-enriched precipitates and a lower number density (~1 x 1023 m-3) of P clusters.