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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2016.1
- 수록면
- 181 - 186 (6page)
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초록· 키워드
오류제보하기
High-Cr ferritic/martensitic (FM) steels are being considered for applications as fuel cladding or core structures for Generation-IV reactors. Because high temperatures approaching 923-973 K (650-700 °C) are envisioned in the designs of Generation IV reactors, irradiation response of high-Cr FM steels at the high temperatures requires investigations. Response of two high-Cr FM steels P92 and 11Cr to irradiation at 973 K (700 °C) was investigated through Ar ion irradiation in combination with damage simulations, nanoindentation measurements and microstructure analyses. Irradiation hardening occurred in both steels after Ar ion irradiation at 973 K (700 °C) to 10 dpa, providing the first evidence that irradiation hardening can occur at a high irradiation temperature of 973 K (700 °C) in high-Cr FM steels. Argon bubbles with a very high number density and an average diameter of about 2.6-3 nm formed in the two steels after the irradiation. The irradiation hardening occurred in the two steels is attributed to the formation of these high-number-density fine argon bubbles produced by the irradiation homogeneously distributed in the matrix. Difference in the magnitude of irradiation hardening between the two steels was also discussed.
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등록된 정보가 없습니다.
참고문헌 (22)
참고문헌 신청
F. Abe / 1994 / J. Nucl. Sci. Technol 31:279
R. L. Klueh / 2001 / High-Chromium Ferritic and Martensitic Steels for Nuclear Applications / ASTM :5
R. L. Klueh / 2007 / J. Nucl. Mater 371:37
F. Abe / 2008 / Sci. Technol. Adv. Mater 9:013002
M. Igarashi / 1997 / Proc. Int. Conf. on Power Engineering-97 :107
R. L. Klueh / 2001 / High-Chromium Ferritic and Martensitic Steels for Nuclear Applications / ASTM :5
R. L. Klueh / 2007 / J. Nucl. Mater 371:37
F. Abe / 2008 / Sci. Technol. Adv. Mater 9:013002
M. Igarashi / 1997 / Proc. Int. Conf. on Power Engineering-97 :107
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