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Inert matrix fuel — A new challenge for material technology in the nuclear fuel cycle

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Abstract

An innovative nuclear fuel concept for the utilization as energy resources and for the incineration of excess Pu arisings as well as for an effective transmutation of minor actinides (MA's; Am, Np and Cm) is discussed from the aspect of material technology. Stabilized cubic phase ZrO2 and other potential candidate materials for the Inert Matrix are compared in terms of the material properties and other behaviors such as the behavior against irradiation with the relevant information currently available. Strategies for the use of the Inert Matrix Fuel concept in various countries are discussed and compared for their options in nuclear fuel cycle technology.

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Authors and Affiliations

  1. Nuclear Fuel Design Technology Development, Korea Atomic Energy Research Institute, 150 Dukjin-dong, Yusong-ku, 305-353, Taejeon, Korea

    Young-Woo Lee, Chang Young Joung, Si Hyung Kim & Sang-Chul Lee

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  1. Young-Woo Lee
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  2. Chang Young Joung
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  3. Si Hyung Kim
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  4. Sang-Chul Lee
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Additional information

This article based on a presentation made in the “Symposium on Nuclear Materials and Fuel 2000” held at the Korea Atomic Energy Research Institute (KAERI), Taejon, Korea, August 24–25, 2000 under the auspices of the Ministry of Science and Technology (MOST).

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Lee, YW., Joung, C.Y., Kim, S.H. et al. Inert matrix fuel — A new challenge for material technology in the nuclear fuel cycle. Met. Mater. Int. 7, 159–164 (2001). https://doi.org/10.1007/BF03026954

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