JAEA-Review-2010-065.pdf:15.99MB - 日本原子力研究開発機構
JAEA-Review-2010-065.pdf:15.99MB - 日本原子力研究開発機構
JAEA-Review-2010-065.pdf:15.99MB - 日本原子力研究開発機構
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1-26<br />
Effect of Temperature Change on Irradiation<br />
Hardening of Ferritic and Austenitic Steels during<br />
Ion-irradiation<br />
S. Jitsukawa a) , M. Ando b) , I. Ioka a) , Y. Abe a) , T. Onitsuka a, c) , N. Ishikawa a) and N. Okubo a)<br />
a) Division of Fuels and Materials Engineering, NSED,<br />
b) Division of Fusion Reactor Engineering, FRDD, c) NSRC, <strong>JAEA</strong><br />
It has been reported that change of irradiation condition (e.g.<br />
irradiation temperature and damage rate) affects microstructural<br />
and property changes of metals and alloys 1) . It may accelerate<br />
irradiation hardening to reduce residual ductility leading<br />
quasi-brittle fracture. Effect of temperature change on the<br />
irradiation hardening is examined.<br />
An 8Cr-2W (0.1C-8Cr-2W-VTa) reduced activation ferritic<br />
steel F82H (developed by <strong>JAEA</strong> and JFE corporation), F82H<br />
doped with 1wt%-Ni (F82H+1Ni) and a type 316 stainless steel<br />
316F (0.04C-0.04Si-17Cr-14Ni-2Mo) were used. Both F82H<br />
and F82H+1Ni were normalized at 1313 K. This was<br />
followed by tempering at 1023 K for 1.5 h. 316F was used<br />
after solution annealing at 1323 K for 1 h. Plates of the alloys<br />
were cut into those of 3 mm × 6 mm × 0.75 mm in size, and<br />
irradiation was conducted on the rectangular surfaces of 6 mm<br />
× 0.75 mm at temperatures of 523 K to 653 K with 10.5 MeV<br />
Fe 3+ ions as well as He and H ions. Average damage rate was<br />
1.0E-3 dpa/s at a depth of 1 m; the projected range for Fe 3+<br />
ions was of about 2 m.<br />
Two accumulated damage levels of 9 dpa (displacement of<br />
atom) and 20 dpa were selected. For 9 dpa specimens,<br />
irradiation temperatures of 573 K and 648 K were applied.<br />
Also, temperature was changed for some of the specimens<br />
between these temperatures during irradiation. For 20 dpa<br />
specimens, 523 K and 653 K were applied. Temperature was<br />
changed between these two temperatures for some of the<br />
specimens. Temperature changes were performed at every<br />
3 dpa, as seen in Fig. 1. The number of temperature changes<br />
were 3 and 6 for 9 dpa and 20 dpa specimens, respectively.<br />
Ultra-micro hardness testing was conducted after irradiation<br />
at the ion-incident surfaces. Penetration depth of 1 m was<br />
kept for all the tests to minimize the effect of the depth<br />
distribution of the irradiation damage. The Ultra-microhardness<br />
testing machine of EMT-1100a (Elionics) was used<br />
for the tests.<br />
Hardness values after irradiation was shown in Fig. 2. The<br />
figure indicates the increment of hardness during irradiation.<br />
Both temperature dependence and damage level dependence of<br />
hardening for 316F was relatively small, although it exhibited<br />
hardening by 1.5 GPa. F82H specimens irradiated at<br />
temperatures cyclically changed exhibited maximal hardening.<br />
The response of F82H+1Ni specimens was rather complicated.<br />
Hardening attained maximal after 20 dpa by temperature change,<br />
while it was smaller than the others at 9 dpa.<br />
Temperature dependence of hardness after irradiation to<br />
10 dpa for F82H was plotted in Fig. 3. Figure indicates that<br />
irradiation hardening attained maximal after irradiation to<br />
10 dpa at temperatures of 673 K. It was also indicated that<br />
hardening by ion-irradiation tends to exhibit maximal at<br />
temperatures of between 623 K and 673 K for these steels 4) .<br />
These suggest that temperature change enhanced irradiation<br />
<strong>JAEA</strong>-<strong>Review</strong> <strong>2010</strong>-065<br />
- 30 -<br />
hardening. It has been also reported that temperature change<br />
during irradiation caused acceleration of irradiation induced<br />
1- 5)<br />
microstructural change and hardening . Several authors<br />
have reported that the effects decreased with damage levels.<br />
Results in Fig. 2, however, indicated different tendencies.<br />
Irradiation hardening often reduces residual ductility and<br />
fracture toughness of the materials. Results by fission reactor<br />
irradiation experiments indicate that residual ductility is not<br />
small and the margin to ductile fracture remains to be<br />
reasonable level even after irradiation to some tens of dpas at<br />
6, 7)<br />
temperatures where irradiation hardening occurs . However,<br />
it should be noted that residual capability of work hardening is<br />
also rather limited and the additional hardening may reduce<br />
residual ductility to a considerable degree.<br />
Fig. 1 Pattern of the<br />
temperature change.<br />
Temperature was<br />
reduced every 3 dpa<br />
and recovered.<br />
573 573-648 648K 523 523-653 653K<br />
Fig. 2 Hardening at constant and cyclically changed temperature.<br />
Fig. 3 Temperature<br />
dependence of<br />
hardening at 10<br />
dpa.<br />
References<br />
1) Y. Yoshida et al., J. Nucl. Mater. 212-215 (1994) 471-475.<br />
2) S. Jitsukawa et al., J. Nucl. Mater. 307-311 (2002) 179-186.<br />
3) S. Jitsukawa et al., J. Nucl. Mater. 329-333 (2004) 39-46.<br />
4) M. Ando, private communication.<br />
5) S. Jitsukawa et al., J. Nucl. Mater. 367-370 (2007) 539-543.<br />
6) K. Suzuki et al., Nucl. Eng. Design 240 (<strong>2010</strong>) 1290-1305.<br />
7) S. Jitsukawa et. al., Nuclear Fusion 49 (2009) 115006.