Swelling Behavior of Commercial Ferritic Alloys, EM-12 and HT-9, as Assessed by Heavy Ion Bombardment

Smidt, F.A.; Malmberg, P. R.; Sprague, J.A.; Westmoreland, J.E.

doi:10.1520/stp38051s

Cited by 24 publications

(5 citation statements)

References 3 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Using ion irradiation at 550°C a peak swelling of 4.7% was observed at 250 dpa, revealing an ion-induced steady-state swelling rate of 0.017%/dpa [43]. Based on these few data and the current observations alone it is not yet possible to confidently predict the swelling or swelling rate for HT-9 at high exposures and the full range of reactor-relevant temperatures.…”

Section: Discussionmentioning

confidence: 74%

Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF

Sencer

Kennedy

Cole

et al. 2011

Journal of Nuclear Materials

View full text Add to dashboard Cite

Section: Discussionmentioning

confidence: 74%

Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF

Sencer

Kennedy

Cole

et al. 2011

Journal of Nuclear Materials

View full text Add to dashboard Cite

“…Ion irradiation, in addition to offering the benefits of accelerated damage rate and excellent temperature control, can provide systematic data sets that can be easily integrated into rate theory models [1,[12][13][14][15][16][17][18]. Furthermore, ion irradiation has been shown to be quite a successful method for emulating reactor damage especially for the purpose of materials selection prior to qualification of in test reactors [1,15,19].…”

Section: Accepted Manuscriptmentioning

confidence: 99%

The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels

Getto

VanCoevering

Was

2017

Journal of Nuclear Materials

View full text Add to dashboard Cite

Understanding the void swelling and phase evolution of reactor structural materials at very high damage levels is essential to maintaining safety and longevity of components in Gen IV fast reactors. A combination of ion irradiation and modeling was utilized to understand the microstructure evolution of ferritic-martensitic alloy HT9 at high dpa. Self-ion irradiation experiments were performed on alloy HT9to determine the co-evolution of voids, dislocations and precipitates up to 650 dpa at 460°C. Modeling of microstructure evolution was conducted using the modified Radiation Induced Microstructure Evolution (RIME) model, which utilizes a mean field rate theory approach with grouped cluster dynamics.Irradiations were performed with 5 MeV raster-scanned Fe 2+ ions on samples pre-implanted with 10 atom parts per million He. The swelling, dislocation and precipitate evolution at very high dpa was determined using Analytical Electron Microscopy in Scanning Transmission Electron Microscopy (STEM) mode.Experimental results were then interpreted using the RIME model. A microstructure consisting only of dislocations and voids is insufficient to account for the swelling evolution observed experimentally at high damage levels in a complicated microstructure such as irradiated alloy HT9. G phase was found to have a minimal effect on either void or dislocation evolution. M 2 X plays two roles; a variable biased sink for defects, and as a vehicle for removal of carbon from solution, thus promoting void growth. When accounting for all microstructure interactions, swelling at high damage levels is a dynamic process that continues to respond to other changes in the microstructure as long as they occur.

show abstract

“…A value of 40 eV displacement threshold energy and the Kinchin-Pease option were used for the damage calculations [29,30]. The irradiation temperature was controlled to be 475 ± 10 ºC to maximize swelling based on previous determinations of peak swelling temperatures [25,[31][32][33]. The chamber vacuum during irradiation was better than 1×10 -6 torr.…”

Section: Experiments Proceduresmentioning

confidence: 99%

Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation

Chen

Aydoğan

Gigax

et al. 2015

Journal of Nuclear Materials

View full text Add to dashboard Cite

A dual-phase 12Cr oxide-dispersion-strengthened (ODS) alloy, with improved corrosion and oxidation resistance exhibits promising void swelling resistance and microstructural stability under Fe 2+ ion irradiation to 800 dpa at 475 ∘C. Dispersoids were originally present in both ferrite and tempered martensite grains, with the latter having a wider range of dispersoid sizes. In both phases dispersoids> 10 nm in diameter are incoherent with the matrix, while smaller dispersoids are coherent. During irradiation the larger incoherent dispersoids shrank and disappeared. Beyond 60 dpadispersoids in both phases approached a near-identical equilibrium size of ~2-2.5 nm, which appears to be rather independent of local displacement rate. Grain morphology was found to be stable under irradiation. Compared to other ferritic-martensitic alloys, the ion-induced swelling of this alloy is quite low, arising from swelling resistance associated with both tempered martensite and dispersoids in both phases, with the swelling in tempered martensite being an order of magnitude less than in the ferrite phase.

show abstract

Swelling Behavior of Commercial Ferritic Alloys, EM-12 and HT-9, as Assessed by Heavy Ion Bombardment

Cited by 24 publications

References 3 publications

Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF

Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF

The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels

Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation

Contact Info

Product

Resources

About