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      고연소도 신형 Zr피복관의 미세조직과 기계적 특성에 미치는 열처리 및 중서자 조사의 영향 = Research Effects of Annealing and Neutron Irradiation on Micostructural and Mechanical Properties of High Burn-up Zr Claddings

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      https://www.riss.kr/link?id=A40101671

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      다국어 초록 (Multilingual Abstract)

      The changes of microstructural and mechanical properties were evaluated for the high bum-up fuel claddings after the neutron irradiation of 1.8-3.1×10^(20)n/㎠ (E>1.O 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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      The changes of microstructural and mechanical properties were evaluated for the high bum-up fuel claddings after the neutron irradiation of 1.8-3.1×10^(20)n/㎠ (E>1.O MEV) in HANARO research reactor. After the irradiation, the spot-type dislocati...

      The changes of microstructural and mechanical properties were evaluated for the high bum-up fuel claddings after the neutron irradiation of 1.8-3.1×10^(20)n/㎠ (E>1.O 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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      참고문헌 (Reference)

      1 "Zirconium in the Nuclear Industry" 1354 : 505-, 2000

      2 "Zirconium in the Nuclear Industry" 1354 : 51-, 2000

      3 "Zirconium in the Nuclear Industry" 1295 : 603-, 1996

      4 "Zirconium in the Nuclear Industry" 1295 : 638-, 1996

      5 "Zirconium in the Nuclear Industry" 1354 : 15-, 2000

      6 "Zirconium in the Nuclear Industry" 437-, 1994

      7 "Zirconium in the Nuclear Industry" 1423 : 471-, 2002

      8 "Zirconium in the Nuclear Industry" 1295 : 710-, 1996

      9 "Zirconium in the Nuclear Industry" 724-, 1994

      10 "Zirconium in the Nuclear Industry" 227-, 1989

      1 "Zirconium in the Nuclear Industry" 1354 : 505-, 2000

      2 "Zirconium in the Nuclear Industry" 1354 : 51-, 2000

      3 "Zirconium in the Nuclear Industry" 1295 : 603-, 1996

      4 "Zirconium in the Nuclear Industry" 1295 : 638-, 1996

      5 "Zirconium in the Nuclear Industry" 1354 : 15-, 2000

      6 "Zirconium in the Nuclear Industry" 437-, 1994

      7 "Zirconium in the Nuclear Industry" 1423 : 471-, 2002

      8 "Zirconium in the Nuclear Industry" 1295 : 710-, 1996

      9 "Zirconium in the Nuclear Industry" 724-, 1994

      10 "Zirconium in the Nuclear Industry" 227-, 1989

      11 "Zirconium in the Nuclear Industry" 1423 : 190-, 2002

      12 "Zirconium in the Nuclear Industry" 1423 : 673-, 2002

      13 "Zirconium in the Nuclear Industry" 1354 : 105-, 2000

      14 "Zirconium in the Nuclear Industry" 346-, 1991

      15 "Standard Test Methods for Tensile Testing of Metallic Materials" 2000

      16 "Seminar Materials on Optimized ZIRLO for Next Generation Fuel" 2003

      17 "Proceedings on Korean Nuclear Society 2003 Fall Meeting" 2003

      18 "Irradiation Engineering of Nuclear Fuel and Materials" 1997

      19 "Introduction to Nuclear Fuels" 2001

      20 "Atomic Energy Review" 154 : 547-, 1977

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2024 평가예정 재인증평가 신청대상 (재인증)
      2021-01-01 평가 등재학술지 선정 (계속평가) KCI등재
      2019-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
      2018-12-01 평가 등재후보 탈락 (계속평가)
      2017-12-01 평가 등재후보로 하락 (계속평가) KCI등재후보
      2013-01-01 평가 등재 1차 FAIL (등재유지) KCI등재
      2010-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2008-01-01 평가 등재 1차 FAIL (등재유지) KCI등재
      2005-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      2004-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2002-07-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.15 0.15 0.14
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.15 0.13 0.33 0.17
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