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Activation analysis of a tritium breeding blanket in the Korean fusion demonstration reactor using the SuperMC code

  • Original Paper - Fluids, Plasma and Phenomenology
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Abstract

The tritium breeding blanket of Korean fusion DEMOnstration reactor (K-DEMO) will be used in an extreme environment exposed to a high-temperature plasma of higher than \(10^9\) \(^\circ \hbox {C}\) and 14.1 MeV neutron field. Under these environments, the deterioration of the structural material of the blanket component proceeds, so the periodic replacement of damaged components is inevitable for the sound operation of the blanket. If the replacement cycle is assumed to be 2 years, it should be possible to establish a plan for safety management and waste disposal necessary for replacement by evaluating the radioactivity of blanket components by neutron irradiation during 2 years. In this study, activation analysis of the basic module of the tritium breeding blanket is done using SuperMC code. The inventory of radioactive nuclides generated by neutron irradiation and the activity of nuclides are investigated. Moreover, the temporal evolution of decay heat and dose rate caused by radioactive nuclides is also studied during the decay-cooling period.

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Acknowledgements

The authors would like to thank the Chinese FDS Team, Hefei, China, for providing the Activation and Shutdown Dose Rate Analysis code for the neutronic analysis of this study. This works are funded by Korea government.

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  1. Korea Institute of Fusion Energy, 169-148 Gwahak-ro, Yusung-gu, Daejeon, 34135, South Korea

    Byung Chul Kim

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  1. Byung Chul Kim
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Correspondence to Byung Chul Kim.

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Kim, B.C. Activation analysis of a tritium breeding blanket in the Korean fusion demonstration reactor using the SuperMC code. J. Korean Phys. Soc. 81, 211–220 (2022). https://doi.org/10.1007/s40042-022-00509-8

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  • DOI: https://doi.org/10.1007/s40042-022-00509-8

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