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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

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1-29<br />

Irradiation Hardening in Ion-irradiated Hafnium<br />

Y. Chimi and J. Ogiyanagi<br />

LWR Long-term Reliability Research Unit, NSRC, <strong>JAEA</strong><br />

Pure hafnium metal is used as one of the neutron<br />

absorbers for control rods in commercial light water reactors,<br />

due to long nuclear lifetime and good corrosion resistance.<br />

In recent years, many cracks on the stainless steel sheath of<br />

control rods using hafnium plates have been found in<br />

Japanese boiling water reactors. The cracks might be<br />

caused by irradiation-assisted stress corrosion cracking<br />

(IASCC) due to the tensile stress originated from the<br />

irradiation growth of hafnium. However, the irradiation<br />

behavior of hafnium has been hardly reported in literature so<br />

far. We have investigated the defect production behavior<br />

of hafnium irradiated with energetic electrons, and the<br />

displacement threshold energy for hafnium was estimated as<br />

E d = 28 eV 1) . In the present work, in order to study the<br />

irradiation behavior of mechanical properties in hafnium, the<br />

irradiation hardening in hafnium irradiated with energetic<br />

heavy-ions has been investigated.<br />

Polycrystalline hafnium plates and rods were used as<br />

specimens. Hafnium plates with ~1 mm in thickness were<br />

cut into small pieces (~5 mm 5 mm), and hafnium rods<br />

with ~5 mm and ~3 mm in diameter (denote as “rod-1” and<br />

“rod-2”, respectively) were cut into disk shape with ~1 mm<br />

in thickness. A plane surface of each specimen was<br />

mechanically and chemically polished.<br />

Ion irradiation of the specimen was performed with<br />

12.0 MeV 56 Fe 4+ ions at 290 °C up to the ion fluence of<br />

9.4 10 15 cm -2 by using a 3-MV tandem accelerator in<br />

TIARA, <strong>JAEA</strong>-Takasaki. The projected range of the ions<br />

is ~2.5 m and the maximum damage cross-section is<br />

2.5 10 -15 cm 2 at a depth of 2.4 m from the specimen<br />

surface, based on the calculation using SRIM code (using<br />

1)<br />

Ed=28 eV ). Therefore, the maximum irradiation dose and<br />

dose rate are estimated to be ~23 dpa and ~7 10 -4 dpa/s,<br />

respectively. In order to eliminate the effect of temperature<br />

history of the specimen, a part of each specimen was<br />

masked by thick metal plate not to be irradiated.<br />

For observation of irradiation hardening in the<br />

ion-irradiated specimen, indentation tests were performed at<br />

room temperature using the UMIS-2000 (CSIRO, Australia)<br />

ultra micro-indentation testing system with Berkovich-type<br />

indenter tip. Indentation depth of 500 nm (corresponding<br />

to indentation load of around 25 mN) was adopted to<br />

observe only the damaged region in the specimen.<br />

Indentation measurements were carried out ~10 times at<br />

intervals of 20 m in both the irradiated and un-irradiated<br />

regions for each specimen.<br />

The results of micro-indentation hardness for<br />

ion-irradiated hafnium specimens are shown in Fig. 1 as a<br />

function of ion fluence. For hafnium plate specimen, the<br />

values of micro-hardness are higher than those for rod<br />

<strong>JAEA</strong>-<strong>Review</strong> <strong>2010</strong>-065<br />

- 33 -<br />

specimens because of the difference of texture caused by the<br />

different manufacturing processes between plate and rod<br />

materials. A large increase in micro-hardness was<br />

observed at the ion fluence of ~ 4 10 14 cm -2 , corresponding<br />

to ~1 dpa at a peak of damage profile. Above ~ 4 <br />

10 14 cm -2 , micro-hardness shows gradual increase with ion<br />

fluence, and has not been saturated even at 9.4 10 15 cm -2<br />

(~ 23 dpa).<br />

For comparison, results for a hafnium rod specimen<br />

irradiated at 190 °C are also shown in Fig. 1. The<br />

micro-hardness for 190 °C irradiation is a little smaller than<br />

those for 290 °C irradiation, whereas the values of<br />

micro-hardness in the un-irradiated region are in the same<br />

range for both 190 °C and 290 °C irradiations.<br />

Irradiation hardening behavior we have observed for pure<br />

hafnium metals is strongly concerned with the evolution of<br />

point defects, defect clusters and dislocation loops, which is<br />

affected by the irradiation temperature, dose and dose rate.<br />

In order to evaluate and clarify the irradiation behavior<br />

including irradiation hardening and also irradiation growth,<br />

it is necessary to understand the relationship between<br />

mechanical property change and microstructural evolution.<br />

Reference<br />

1) Y. Chimi et al., <strong>JAEA</strong> Takasaki Ann. Rep. 2008 (2009)<br />

37.<br />

Micro-hardness (GPa)<br />

5<br />

4<br />

3<br />

Hf plate<br />

Hf rod-1<br />

Hf rod-2<br />

Hf rod-1(190°C)<br />

0 5<br />

Ion fluence (10<br />

10<br />

15 cm -2 )<br />

Fig. 1 Ion fluence dependence of micro-hardness<br />

for ion-irradiated hafnium (Hf) plate and rods.<br />

Dotted lines are guides for the eye.

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