Some Implications of Radiation-Induced Property Changes in Austenitic Stainless Steels on ITER First-Wall Design and Performance

1991 ◽  
Vol 19 (3P2B) ◽  
pp. 1571-1579 ◽  
Author(s):  
P.J. Maziasz ◽  
A.F. Rowcliffe ◽  
M.L. Grossbeck ◽  
G.E.C. Bell ◽  
E.E. Bloom ◽  
...  
Author(s):  
E. A. Kenik ◽  
K. Hojou

Radiation-induced segregation (RIS) is driven by fluxes of point defects to sinks. RIS can induce composition fluctuations in irradiated stainless steels, which can result in microstructural and property changes, including precipitation, austenite instability, strengthening, embrittlement, and irradiation-assisted sensitization and stress corrosion cracking. Analytical electron microscopy (AEM) provides a powerful technique to study such segregation. RIS in several irradiated stainless steels has been investigated. AEM was performed in a Philips EM400T/FEG equipped with an EDAX 9100/70 analysis system. The specimens were neutron irradiated to 15 displacements per atom (dpa) at 520 ° C in the Fast Flux Test Facility (FFTF) and were only mildly radioactive (<50/μCi = 1.85 MBq), thus permitting high spatial resolution X-ray microanalysis to be employed. Typical acquisitions were performed for 100 s in the STEM mode with <2-nm-diam probes containing >0.5 nA current. Subtraction of “in-hole” spectra from the measured spectra corrected for both the normal “in-hole” counts and those associated with the radioactivity of the specimen.


2008 ◽  
Vol 79 (6) ◽  
pp. 423-432 ◽  
Author(s):  
Cameron B. Tague ◽  
Martin C. Mataya ◽  
David K. Matlock ◽  
George Krauss

2007 ◽  
Vol 124-126 ◽  
pp. 1661-1664
Author(s):  
Deuck Seung Bae ◽  
Woo Sang Jung ◽  
Suk Woo Hong ◽  
Sang Min Song ◽  
Soon Hyo Chung ◽  
...  

Ferritic steels have been candidate structural materials for first wall and blanket structures of fusion power plant since the late 1970’s, when the fast-reactor irradiation showed them to be more swelling resistant than austenitic stainless steels. In this investigation, the coarsening of MX nitrides during aging was studied for Cr-Mo-N-X(X=V, Nb, Ti) ferritic steels. During the aging, (V, Nb, Ti)nitrides were precipitated out. From TEM observation, particle size distribution was confirmed and size distribution follows a typical log-normal distribution. The coarsening rate of MX nitrides was correlated with the Oswald ripening equation.


1998 ◽  
Vol 540 ◽  
Author(s):  
E. P. Simonen ◽  
S. M. Bruemmer

AbstractInteractions between point defects and major solute strongly influence grain boundary concentrations during heat treatment, irradiation and annealing of austenitic stainless steels. Previous approaches to nonequilibrium segregation emphasize only elastic defect-solute interactions. The present evaluation of nonequilibrium concentrations at grain boundaries indicates chemical interactions unique to solution annealing and cooling during thermal nonequilibrium segregation (TNES). Subsequent to TNES, radiation-induced segregation and post-irradiation annealing are modeled and compared with measured changes in grain boundary composition. The latter two mechanisms are controlled by exchanges between vacancies and major solute such as Cr.


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