• 방사성폐기물학회지
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• 제3권3호
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• pp.201-211
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• 2005

본 연구에서는 사용후 TRISO 연료 처리를 위한 보다 효과적인 공정개발을 위하여 기존 전처리 기술에 대한 검토를 수행하였다. TRISO 연료 처리에 있어서 가장 중요한 사항은 연료입자에 포함되어 있는 탄소와 SiC성분을 효과적으로 분리하는데 있다. 공정개발 초기에 고려되었던 분쇄 후 배소공정의 경우 $^{14}C$ 처리공정에서 발생되는 2차 폐기물로 인하여 분쇄 후 침출공정으로 대체 되었으나 여전히 해결해야 될 근본적인 문제점이 존재하고 있다. 따라서 본 논문에서는 TRISO 입자의 피복층 제거를 위한 새로운 개념의 열적 파쇄와 용융염 전해반응에 의한 피복층 제거 공정을 제안하였으며 각 공정에 대한 원리를 자세하게 기술하였다.

• 한국세라믹학회지
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• 제51권5호
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• pp.435-441
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• 2014

Silicon carbide-based ceramics and their composites have been studied for application to fusion and advanced fission energy systems. For fission reactors, $SiC_f$/SiC composites can be applied to core structural materials. Multilayered SiC composite fuel cladding, owing to its superior high temperature strength and low hydrogen generation under severe accident conditions, is a candidate for the replacement of zirconium alloy cladding. The SiC composite cladding has to retain its mechanical properties and original structure under the inner pressure caused by fission products; as such it can be applied as a cladding in fission reactor. A hoop strength test using an expandable polyurethane plug was designed in order to evaluate the mechanical properties of the fuel cladding. In this paper, a hoop strength test of the multilayered SiC composite tube for nuclear fuel cladding was simulated using FEA. The stress caused by the plug was distributed nonuniformly because of the friction coefficient difference between the inner surface of the tube and the plug. Hoop stress and shear stress at the tube was evaluated and the relationship between the concentrated stress at the inner layer of the tube and the fracture behavior of the tube was investigated.