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핵연료 피복관용 지르칼로이-4의 미세조직과 기계적 특성에 미치는 β-열처리의 영향 KCI 등재 SCOPUS

The Effect of β-Heat Treatment on the Microstructure and Mechanical Characteristics of Zircaloy-4 for Nuclear Fuel Cladding

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한국재료학회지 (Korean Journal of Materials Research)
한국재료학회 (Materials Research Society Of Korea)
초록

The effect of β-heat treatment on th microstructure, mechanical properties and texture in the nuclear fuel cladding of Zircaloy-4 tubes was chosen at 1000, 1100 and 1200˚C, and the tubes were heat-treated by a high frequency vacuum induction furnace. Morphology of the second phase particles and α-grain of as-received tubes were markedly changed by heat treatment. The average sizes of second phase particles of as-received and β-heat treated tubes were 0.1μm and 0.076μm, respectively. However, the average sizes of second phase particles were not much changed in the β-heated temperatures. With increasing heat treatment temperatures, the 0.2% yield strength and the hoop strength were decreased because of changes in preferred orientation as will as α-plate width. Heat treated Zircaloy-4 tubes exhibited texture changes but the preferred orientation of grains still remained.

저자
  • 고진현
  • 오영근 | 오영근
  • 김광수 | 김광수