2000
DOI: 10.1016/s0022-3115(99)00225-1
|View full text |Cite
|
Sign up to set email alerts
|

Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1
1
1
1

Citation Types

20
270
2
1

Year Published

2006
2006
2024
2024

Publication Types

Select...
7
2

Relationship

0
9

Authors

Journals

citations
Cited by 498 publications
(312 citation statements)
references
References 46 publications
20
270
2
1
Order By: Relevance
“…Two Fe-Cr alloys with different Cr content have been investigated. The wellknown effect of chromium on the corrosion resistance of the steels is more pronounced for the specimen with higher Cr content [17][18][19]. This was the reason why we focused on comparison of two alloys with different Cr content in our studies.…”
Section: Resultsmentioning
confidence: 99%
“…Two Fe-Cr alloys with different Cr content have been investigated. The wellknown effect of chromium on the corrosion resistance of the steels is more pronounced for the specimen with higher Cr content [17][18][19]. This was the reason why we focused on comparison of two alloys with different Cr content in our studies.…”
Section: Resultsmentioning
confidence: 99%
“…Recent reviews of the theory of radiation damage [23][59] along with extensive data and interpretation [23] indicate this provides an opportunity for research into the mechanisms of time-dependent microstructure evolution in the presence of irradiation effects. Even though microscale [18][24] [59] and macroscale [36] descriptions of void swelling exist, it is still not feasible to predict a priori the sudden onset of void swelling as functions of imposed state variables.…”
Section: Radiation Damage In Nuclear Materialsmentioning
confidence: 99%
“…This technique, which operates at the length scale of microns and the time scale of seconds, seems well suited to simultaneously probing the elastic and thermal properties of irradiated metals, just microns below the free surface [36]. Considering that existing ex-situ datasets on void swelling are relatively sparse, time-resolved data in situ clearly would be very useful.…”
Section: Mesoscale Science In Materials Agingmentioning
confidence: 99%
“…lower than that of austenitic steels austenitic steels (~1%/dpa), is has been attributed to the fact that austenitic steels have an fcc structure and void nucleation proves to be more difficult in the F/M bcc structure. These commonly held concepts have been reviewed recently [20]. It has been shown that the incubation period is much longer for F/M steels especially when irradiated under wellcontrolled temperature conditions, (as in the case of FFTF experiments), but then these steels swell to at an accelerated rate of ~ 0.2%/dpa and possibly greater.…”
Section: Temperature and Dose Limits For Swelling In Ht-9 And T-91mentioning
confidence: 99%