TY - JOUR
T1 - A dual ion irradiation study of helium-dpa interactions on cavity evolution in tempered martensitic steels and nanostructured ferritic alloys
AU - Yamamoto, Takuya
AU - Wu, Yuan
AU - Robert Odette, G.
AU - Yabuuchi, Kiyohiro
AU - Kondo, Sosuke
AU - Kimura, Akihiko
N1 - Funding Information:
The dual ion-beam irradiations were initially conducted in the TITAN program for US DOE- Japan MEXT collaboration for fusion energy research and continued under the support of the “Joint Research Program on Zero-Emission Energy Research, Institute of Advanced Energy, Kyoto University (ZE24A-13 and 23B-3). The work performed at UCSB was supported by the U. S. Department of Energy, Office of Fusion Energy Sciences, under contract DE-FG03-94ER54275. We acknowledge the contributions of the NSF sponsored UCSB Microstructure and Microanalysis Facility. We are also grateful for generous support of research materials, F82H mod.3 from Dr. K. Shiba, (JAEA, Japan), MA957 from Dr. R.J. Kurtz (PNNL) and 14YWT-PM2 from Dr. D.T. Hoelzer (ORNL).
PY - 2014/6
Y1 - 2014/6
N2 - Cavity evolutions in a normalized and tempered martensitic steel (TMS) and two nanostructured ferritic alloys (NFA) under Fe3+ and He + dual ion beam irradiations (DII) at 500 °C and 650 °C were characterized. The irradiation conditions encompass a wide range of displacement per atom damage (dpa), He and He/dpa. The 500 °C DII produced damage and He levels of ≈10-47 dpa and ≈400-2000 appm, respectively. Transmission electron microscopy (TEM) showed that DII of a 8Cr TMS, at 500 °C to up to 60 dpa and 2100 appm He, produced a moderate density of non-uniformly distributed cavities with bimodal sizes ranging from ≈1 nm He bubbles to ≈20 nm faceted voids, and swelling ≈0.44%. In contrast, the same irradiation conditions produced only small ≈1.3 nm diameter bubbles and swelling of ≈0.05% in the NFA MA957. Similar bubble distributions were observed in MA957 and a developmental NFA DII at 650 °C up to ≈80 dpa and ≈3900 appm He. These results demonstrate the outstanding He management capability of the oxide nano-features in the NFA. The various data trends are shown as a function of dpa, He, He/dpa and He*dpa.
AB - Cavity evolutions in a normalized and tempered martensitic steel (TMS) and two nanostructured ferritic alloys (NFA) under Fe3+ and He + dual ion beam irradiations (DII) at 500 °C and 650 °C were characterized. The irradiation conditions encompass a wide range of displacement per atom damage (dpa), He and He/dpa. The 500 °C DII produced damage and He levels of ≈10-47 dpa and ≈400-2000 appm, respectively. Transmission electron microscopy (TEM) showed that DII of a 8Cr TMS, at 500 °C to up to 60 dpa and 2100 appm He, produced a moderate density of non-uniformly distributed cavities with bimodal sizes ranging from ≈1 nm He bubbles to ≈20 nm faceted voids, and swelling ≈0.44%. In contrast, the same irradiation conditions produced only small ≈1.3 nm diameter bubbles and swelling of ≈0.05% in the NFA MA957. Similar bubble distributions were observed in MA957 and a developmental NFA DII at 650 °C up to ≈80 dpa and ≈3900 appm He. These results demonstrate the outstanding He management capability of the oxide nano-features in the NFA. The various data trends are shown as a function of dpa, He, He/dpa and He*dpa.
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U2 - 10.1016/j.jnucmat.2014.01.040
DO - 10.1016/j.jnucmat.2014.01.040
M3 - Article
AN - SCOPUS:84901203589
SN - 0022-3115
VL - 449
SP - 190
EP - 199
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
IS - 1-3
ER -