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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.

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