Dose Dependence of Radiation Induced Segregation in Proton Irradiated Austen1tic Alloys

1996 ◽  
Vol 439 ◽  
Author(s):  
J. T. Busby ◽  
T. R. Allen ◽  
R. D. Carter ◽  
E. A. Kenik ◽  
G. S. Was

AbstractThe dose dependence of radiation-induced segregation (RIS) is investigated for proton irradiated ultra high-purity (UHP) 304L stainless steel and Fe-20Cr-24Ni. Grain boundary compositions were measured in samples irradiated with 3.2 MeV protons at 400°C to doses ranging from 0.1 to 3.0 dpa. RIS measurements were made using scanning transmission electron microscopy with energy dispersive x-ray spectroscopy (STEM/EDS) and compared to results from Auger electron spectroscopy (AES). Comparison of the dose dependence for HP-304L and Fe- 20Cr-24Ni shows that RIS is alloy specific. The approach to steady-state Cr depletion was observed to be more rapid in the alloy with higher Ni content. Fe-2OCr-24Ni reaches a steady-state Cr depletion level by 0.5 dpa, and the amount of Cr depletion in HP-304L SS is still increasing between 1.0 and 3.0 dpa. RIS in the stainless steel alloys irradiated with 3.2 MeV protons is comparable to that in neutron irradiated steels of similar composition.

1999 ◽  
Vol 275 (1) ◽  
pp. 115-118 ◽  
Author(s):  
J Chen ◽  
Y Dai ◽  
F Carsughi ◽  
W.F Sommer ◽  
G.S Bauer ◽  
...  

1999 ◽  
Vol 589 ◽  
Author(s):  
E.A. Kenik ◽  
J.T. Busby ◽  
G.S. Was

AbstractThe spatial redistribution of alloying elements and impurities near grain boundaries in several stainless steel alloys arising from non-equilibrium processes have been measured by analytical electron microscopy (AEM) in a field emission scanning transmission electron microscope. Radiation-induced segregation (RIS) has been shown to result in significant compositional changes at point defects sinks, such as grain boundaries. The influence of irradiation dose and temperature, alloy composition, prior heat treatment, and post-irradiation annealing on the grain boundary composition profiles have been investigated. Understanding the importance of these microchemical changes relative to the radiation-induced microstructural change in irradiation-assisted stress corrosion cracking (IASCC) of the irradiated materials is the primary goal of this study.


2001 ◽  
Vol 296 (1-3) ◽  
pp. 174-182 ◽  
Author(s):  
Y Dai ◽  
X Jia ◽  
J.C Chen ◽  
W.F Sommer ◽  
M Victoria ◽  
...  

2021 ◽  
Vol 7 (13) ◽  
pp. eabf6771
Author(s):  
M. A. Tunes ◽  
M. Imtyazuddin ◽  
C. Kainz ◽  
S. Pogatscher ◽  
V.M. Vishnyakov

A dual-phase Cr2AlC material was synthesized using magnetron sputtering at a temperature of 648 K. A stoichiometric and nanocrystalline MAX phase matrix was observed along with the presence of spherical-shaped amorphous nano-zones as a secondary phase. The irradiation resistance of the material was assessed using a 300-keV Xe ion beam in situ within a transmission electron microscope up to 40 displacements per atom at 623 K: a condition that extrapolates the harmful environments of future fusion and fission nuclear reactors. At the maximum dose investigated, complete amorphization was not observed. Scanning transmission electron microscopy coupled with energy-dispersive x-ray revealed an association between swelling due to inert gas bubble nucleation and growth and radiation-induced segregation and clustering. Counterintuitively, the findings suggest that preexisting amorphous nano-zones can be beneficial to Cr2AlC MAX phase under extreme environments.


Author(s):  
L. E. Thomas

G and n phases are complex nickel silicides which commonly form in Fe-Ni-Cr based stainless steels and superalloys during neutron irradiation at 400-600°C. Both phases are cubic and are structurally similar to the common carbides M2 3C6 and M6C which form in many of the same alloys during thermal aging. Although G and n have been analyzed previously by energy-dispersive x-ray spectrometry (EDXS), little is known about their carbon contents.To further determine the compositional relationships between the G/n silicides and the M 23C 6/M6C carbides, an irradiated Ti-modified 316 stainless steel specimen containing 0.05 to 0.5μm particles of G and n was analyzed by means of electron energy loss spectroscopy (ELS) and EDXS in a field emission gun scanning transmission electron microscope (STEM). The alloy, LSI, has the nominal composition of Fe-16.8Cr-13.5Ni-l.9Mo-0.87Si-2.0Mn-.15Ti-.045C and was irradiated to 2 x 1022n/cm2, E >0.1 MeV, at 510°C in the EBR-II breeder test reactor.


2013 ◽  
Vol 1514 ◽  
pp. 93-98 ◽  
Author(s):  
Seiya Takaki ◽  
Tomokazu Yamamoto ◽  
Masanori Kutsuwada ◽  
Kazuhiro Yasuda ◽  
Syo Matsumura

ABSTRACTWe have investigated the atomistic structure of radiation-induced defects in CeO2 formed under 200 keV electron irradiation. Dislocation loops on {111} habit planes are observed, and they grow accompanying strong strain-field. Atomic resolution scanning transmission electron microscopy (STEM) observations with high angle annular dark-field (HAADF) and annular bright-field (ABF) imaging techniques showed that no additional Ce layers are inserted at the position of the dislocation loop, and that strong distortion and expansion is induced around the dislocation loops. These results are discussed that dislocation loops formed under electron irradiation are non-stoichiometric defects consist of oxygen interstitials.


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