Page 1. CORROSION TESTING IN SUPPORT OF THE ACCELERATOR PRODUCTION OF TRITIUM PROGRAM GT Chandler... more Page 1. CORROSION TESTING IN SUPPORT OF THE ACCELERATOR PRODUCTION OF TRITIUM PROGRAM GT Chandler, KA Dunn, MR Louthan, Jr., and JT Mickalonis Westinghouse Savannah River Technology Center Aiken, SC 29808 ...
... Xiao, and AH Heuer Case Western Reserve University, Cleveland, Ohio 44106 J. Garrett McMaster... more ... Xiao, and AH Heuer Case Western Reserve University, Cleveland, Ohio 44106 J. Garrett McMaster University, Hamilton, Ontario L8S 4M1, Canada ... the misfits associated with the three different types of interfaces can be calculated (see Table I) according to Brooks' formula6 ...
Overcoming radiation damage degradation is a key rate-controlling step in fusion materials develo... more Overcoming radiation damage degradation is a key rate-controlling step in fusion materials development. New science, approaches, and facilities are needed at multiple scales. Understanding is needed at the atomic scale of the behavior of materials subject to extreme radiation doses and mechanical stress in order to synthesize new materials that can tolerate such conditions. Current computational and experimental research into radiation-tolerant materials will be described. Plans for future irradiation facilities and science are also described. The Matter Radiation Interactions in Extremes (MaRIE) concept is a National User Facility to realize the vision of 21 st century materials research and development. The Fission and Fusion Materials Facility (F 3) segment of MaRIE proposes to use the present proton linac at Los Alamos with a power upgrade to drive a spallation neutron source that can provide the required radiation environment. Importantly, F 3 would also provide the capability ...
... NM, 87545, 2001, 20 p. [2] SA Maloy, WF Sommer, MR James, T. Romero, M. Lopez, E. Zimmermann ... more ... NM, 87545, 2001, 20 p. [2] SA Maloy, WF Sommer, MR James, T. Romero, M. Lopez, E. Zimmermann and J. Ledbetter, Nucl. Technol. 132 (2000), p. 103. View Record in Scopus | Cited By in Scopus (6). [3] BM Oliver, FA Garner ...
Page 1. Kinetics of the Nucleation and Growth of Helium Bubbles in bcc Iron Chaitanya Suresh Deo ... more Page 1. Kinetics of the Nucleation and Growth of Helium Bubbles in bcc Iron Chaitanya Suresh Deo 1 , Srinivasan G. Srivilliputhur 1 , Michael Baskes 1 , Stuart Maloy 1 , Michael ... [6] H. Trinkaus and BN Singh, Journal of Nuclear Materials, 323, 229-42 (2003). ...
ABSTRACT The remarkable radiation damage resistance of nanostructured ferritic alloys (NFAs) is a... more ABSTRACT The remarkable radiation damage resistance of nanostructured ferritic alloys (NFAs) is attributed to the large numbers of matrix nanofeatures (NFs) of various types, which can enhance the recombination of displacement defects and trap transmutant helium in fine scale bubbles. Characterizing the chemistry, crystallographic structure and orientation relationships of the NFs is critical to understanding how they enhance the radiation damage resistance of NFAs. Conventional and high-resolution transmission electron microscopy and energy-dispersive spectroscopy were used to characterize the various types of NF and larger oxide phases in a model 14Cr–3 W–0.4Ti–0.25Y2O3 NFA (14YWT) hot isostatic pressed (HIP-ed) at 1150°C. Large CrTiO3 precipitates (50–300 nm) and small diffracting NFs (
... GT (Rusty) Gray presented work on high strain rate deformation of Ta, while P. Peralta descri... more ... GT (Rusty) Gray presented work on high strain rate deformation of Ta, while P. Peralta described the use of indentation techniques to elucidate ... half of the session had three talks on radiation damage of metals and ceramics respectively by KE Sickafus/ RW Grimes, C. Kinoshita ...
ABSTRACT Ion beam irradiation is a widely used method to cause radiation damage in materials in o... more ABSTRACT Ion beam irradiation is a widely used method to cause radiation damage in materials in order to study materials degradation under radiation in a laboratory setting. Nanoindentation has become an often used tool to measure the mechanical property changes due to ion beam irradiation. While the combination of ion beam irradiation and nanoindentation is a powerful tool, difficulties arise and need to be discussed in detail. This work intends to draw attention to the potential issues one might face if nanoindentation is used to evaluate radiation induced hardening, especially if compared to other mechanical tests such as yield strength from tensile tests on irradiated materials and others. In this work we focus on issues associated with size and dose effects associated with quasi static nanoindentation on shallow irradiated Cu [1 0 0] single crystal material. It is shown that on 1 μm deep irradiated material it is not possible to correlate a single dose to a specific hardness value, rather a dose range has to be considered. However, deeper indents will always sample contributions of the unirradiated material. Moreover, the correlation between the indentation hardness and macroscopic properties is not straight forward.
ABSTRACT Lead–bismuth eutectic (LBE) liquid metal is considered to act as the coolant and as spal... more ABSTRACT Lead–bismuth eutectic (LBE) liquid metal is considered to act as the coolant and as spallation neutron source for a future accelerator driven system (ADS). In addition to the highly corrosive effect of the liquid lead–bismuth eutectic, the liquid metal may also affect the mechanical integrity of the structural materials by a phenomenon called liquid metal embrittlement. Thus, although the addition of silicon to ferritic–martensitic steels has been found to strongly increase the material’s resistance to corrosion in liquid lead–bismuth environment, their mechanical properties can be strongly affected by the liquid metal environment. This paper discusses the mechanical properties of an experimental silicon enriched high Cr/high creep resistant bainitic steel when in contact with LBE. The steel’s mechanical properties were assessed by tensile testing as function of temperature in both liquid lead–bismuth eutectic and in an argon and hydrogen gas environment. It was found that the silicon enriched bainitic steel is very prone to liquid metal embrittlement between 300 and 375 C with the transition in mechanical behaviour from ductile to predominantly brittle between 200 and 300 C thus defining its the so-called ductility trough.
Page 1. CORROSION TESTING IN SUPPORT OF THE ACCELERATOR PRODUCTION OF TRITIUM PROGRAM GT Chandler... more Page 1. CORROSION TESTING IN SUPPORT OF THE ACCELERATOR PRODUCTION OF TRITIUM PROGRAM GT Chandler, KA Dunn, MR Louthan, Jr., and JT Mickalonis Westinghouse Savannah River Technology Center Aiken, SC 29808 ...
... Xiao, and AH Heuer Case Western Reserve University, Cleveland, Ohio 44106 J. Garrett McMaster... more ... Xiao, and AH Heuer Case Western Reserve University, Cleveland, Ohio 44106 J. Garrett McMaster University, Hamilton, Ontario L8S 4M1, Canada ... the misfits associated with the three different types of interfaces can be calculated (see Table I) according to Brooks' formula6 ...
Overcoming radiation damage degradation is a key rate-controlling step in fusion materials develo... more Overcoming radiation damage degradation is a key rate-controlling step in fusion materials development. New science, approaches, and facilities are needed at multiple scales. Understanding is needed at the atomic scale of the behavior of materials subject to extreme radiation doses and mechanical stress in order to synthesize new materials that can tolerate such conditions. Current computational and experimental research into radiation-tolerant materials will be described. Plans for future irradiation facilities and science are also described. The Matter Radiation Interactions in Extremes (MaRIE) concept is a National User Facility to realize the vision of 21 st century materials research and development. The Fission and Fusion Materials Facility (F 3) segment of MaRIE proposes to use the present proton linac at Los Alamos with a power upgrade to drive a spallation neutron source that can provide the required radiation environment. Importantly, F 3 would also provide the capability ...
... NM, 87545, 2001, 20 p. [2] SA Maloy, WF Sommer, MR James, T. Romero, M. Lopez, E. Zimmermann ... more ... NM, 87545, 2001, 20 p. [2] SA Maloy, WF Sommer, MR James, T. Romero, M. Lopez, E. Zimmermann and J. Ledbetter, Nucl. Technol. 132 (2000), p. 103. View Record in Scopus | Cited By in Scopus (6). [3] BM Oliver, FA Garner ...
Page 1. Kinetics of the Nucleation and Growth of Helium Bubbles in bcc Iron Chaitanya Suresh Deo ... more Page 1. Kinetics of the Nucleation and Growth of Helium Bubbles in bcc Iron Chaitanya Suresh Deo 1 , Srinivasan G. Srivilliputhur 1 , Michael Baskes 1 , Stuart Maloy 1 , Michael ... [6] H. Trinkaus and BN Singh, Journal of Nuclear Materials, 323, 229-42 (2003). ...
ABSTRACT The remarkable radiation damage resistance of nanostructured ferritic alloys (NFAs) is a... more ABSTRACT The remarkable radiation damage resistance of nanostructured ferritic alloys (NFAs) is attributed to the large numbers of matrix nanofeatures (NFs) of various types, which can enhance the recombination of displacement defects and trap transmutant helium in fine scale bubbles. Characterizing the chemistry, crystallographic structure and orientation relationships of the NFs is critical to understanding how they enhance the radiation damage resistance of NFAs. Conventional and high-resolution transmission electron microscopy and energy-dispersive spectroscopy were used to characterize the various types of NF and larger oxide phases in a model 14Cr–3 W–0.4Ti–0.25Y2O3 NFA (14YWT) hot isostatic pressed (HIP-ed) at 1150°C. Large CrTiO3 precipitates (50–300 nm) and small diffracting NFs (
... GT (Rusty) Gray presented work on high strain rate deformation of Ta, while P. Peralta descri... more ... GT (Rusty) Gray presented work on high strain rate deformation of Ta, while P. Peralta described the use of indentation techniques to elucidate ... half of the session had three talks on radiation damage of metals and ceramics respectively by KE Sickafus/ RW Grimes, C. Kinoshita ...
ABSTRACT Ion beam irradiation is a widely used method to cause radiation damage in materials in o... more ABSTRACT Ion beam irradiation is a widely used method to cause radiation damage in materials in order to study materials degradation under radiation in a laboratory setting. Nanoindentation has become an often used tool to measure the mechanical property changes due to ion beam irradiation. While the combination of ion beam irradiation and nanoindentation is a powerful tool, difficulties arise and need to be discussed in detail. This work intends to draw attention to the potential issues one might face if nanoindentation is used to evaluate radiation induced hardening, especially if compared to other mechanical tests such as yield strength from tensile tests on irradiated materials and others. In this work we focus on issues associated with size and dose effects associated with quasi static nanoindentation on shallow irradiated Cu [1 0 0] single crystal material. It is shown that on 1 μm deep irradiated material it is not possible to correlate a single dose to a specific hardness value, rather a dose range has to be considered. However, deeper indents will always sample contributions of the unirradiated material. Moreover, the correlation between the indentation hardness and macroscopic properties is not straight forward.
ABSTRACT Lead–bismuth eutectic (LBE) liquid metal is considered to act as the coolant and as spal... more ABSTRACT Lead–bismuth eutectic (LBE) liquid metal is considered to act as the coolant and as spallation neutron source for a future accelerator driven system (ADS). In addition to the highly corrosive effect of the liquid lead–bismuth eutectic, the liquid metal may also affect the mechanical integrity of the structural materials by a phenomenon called liquid metal embrittlement. Thus, although the addition of silicon to ferritic–martensitic steels has been found to strongly increase the material’s resistance to corrosion in liquid lead–bismuth environment, their mechanical properties can be strongly affected by the liquid metal environment. This paper discusses the mechanical properties of an experimental silicon enriched high Cr/high creep resistant bainitic steel when in contact with LBE. The steel’s mechanical properties were assessed by tensile testing as function of temperature in both liquid lead–bismuth eutectic and in an argon and hydrogen gas environment. It was found that the silicon enriched bainitic steel is very prone to liquid metal embrittlement between 300 and 375 C with the transition in mechanical behaviour from ductile to predominantly brittle between 200 and 300 C thus defining its the so-called ductility trough.
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