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논문 기본 정보

자료유형
학술저널
저자정보
백종혁 (한국원자력연구소 지르코늄신합금 핵연료피복관 개발팀) 김현길 (한국원자력연구소 지르코늄신합금 핵연료피복관 개발팀) 정용환 (한국원자력연구소 지르코늄신합금 핵연료피복관 개발팀)
저널정보
한국열처리공학회 열처리공학회지 열처리공학회지 제17권 제3호
발행연도
2004.1
수록면
151 - 164 (14page)

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The changes of microstructural and mechanical properties were evaluated for the high burn-up fuel claddings after the neutron irradiation of $1.8{\sim}3.1{\times}10^{20}n/cm^2$ (E>1.0 MEV) in HANARO research reactor. After the irradiation, the spot-type dislocations (a-type dislocations) were easily observed in most claddings, and the density of the dislocations was different depending on the grains and was higher at grain boundaries than within grains. As the final annealing temperature increased, the density of spot-type dislocations increased and the line-type dislocations (c-type dislocations) which was perpendicular to the <0002> direction, appeared sporadically in some claddings. However, the types of precipitates in the fuel claddings after the irradiation were not changed from that in unirradiated claddings. The mechanical properties including the hardness, strength and elongation after the irradiation were changed due to the formation of spot-type dislocations. That is, the increase in hardness and strength as well as the decrease in elongation after the irradiation was occurred simultaneously with increasing the final annealing temperature. Owing to the Nb contribution to the formation of spot-type dislocation during the irradiation, the increase in hardness and strength in higher Nb-contained Zr alloys after the irradiation was higher than that in lower Nb-contained Zr alloys.

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