• Title/Summary/Keyword: radioactive metal waste

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The structural and non-linear dynamic analysis for radioactive waste container

  • Yu-Yu Shen;Kuei-Jen Cheng;Hsoung-Wei Chou
    • Nuclear Engineering and Technology
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    • v.55 no.8
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    • pp.3010-3016
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    • 2023

  • In recent years, the development of radioactive waste containers for nuclear facility decommissioning and dismantling is a critical issue because the Taiwan domestic boiling water reactor nuclear power plant is going to be decommissioned. The main purpose of this research is to design a metal container that meets the structural requirements of related regulations. At first, the shielding analysis was performed by varying dimensions of radioactive waste to determine the storage efficiency of the container. Then, a series of structural analyses for operational and accidental conditions of the container with full load were conducted, such as lifting, stacking, and drop impact conditions. On the other hand, the field drop impact tests were carried out to ensure structural integrity. The present research demonstrates the structural safety of the developed container for decommissioned nuclear facilities in Taiwan.

  • https://doi.org/10.1016/j.net.2023.05.004 인용 PDF

THE PERFORMANCE OF CLAY BARRIERS IN REPOSITORIES FOR HIGH-LEVEL RADIOACTIVE WASTE

  • Pusch, Roland
    • Nuclear Engineering and Technology
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    • v.38 no.6
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    • pp.483-488
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    • 2006

  • Highly radioactive waste is placed in metal canisters embedded in dense clay termed buffer. The radioactive decay is associated with heat production, which causes degradation of the buffer and thereby time-dependent loss of its waste-isolating potential. The buffer is prepared by compacting air-dry smectite clay powder and is initially not fully water saturated. The evolution of the buffer starts with slow wetting by uptake of water from the surrounding rock followed by a long period of exposure to heat, pressure from the rock and chemical reactants. It can be described by conceptual and theoretical models describing processes related to temperature (T), hydraulic (H), mechanical (M) and chemical performance (C). For temperatures below 90 C more than 75 % of the smectite will be preserved for 100 000 years but cementation may reduce the excellent performance of the buffer to a yet not known extention.

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Development Status for Commercialization of Spent Nuclear Fuel Transportation and Dry Storage System Technology (사용후핵연료 수송/저장시스템 상용화 기술개발 경과)

  • Baeg, Chang-Yeal;Cho, Chun-Hyung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.16 no.2
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    • pp.271-279
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    • 2018

  • During the seven years from 2009 to 2016, PWR SNF (spent nuclear fuel) transportation and storage systems suitable for domestic conditions were developed by the government to cope with the saturation of wet storage capacity in NPPs. One of the developed systems is a multipurpose metal cask applicable for transportation/storage; the other is a concrete cask dedicated to storage. Efficient cask technologies were secured utilizing the characteristics and experience of relevant industrial, academic and research institutes. Technological independence was also achieved through several patent registrations of research outcomes. To prepare for a rapid increase of demand in the near future, technology transfer of secured patents and technologies to the domestic industry was carried out twice in the years of 2016 and 2017.

  • https://doi.org/10.7733/jnfcwt.2018.16.2.271 인용 PDF KSCI