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Report No.
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Preliminary calculation for dose evaluation at the process of fuel debris retrieval from Fukushima Daiichi Nuclear Power Station

Okumura, Keisuke ; Kojima, Kensuke; Hagura, Hiroyuki*; Ito, Takashi*; Miyoshi, Katsumasa*

In order to contribute to the removal of fuel debris from Fukushima Daiichi Nuclear Power Station (1F), an efficient estimation method of the dose rate distribution in the primary containment vessel of 1F, by using photon transport calculations with a Monte Carlo calculation code and information on the radiation sources obtained from computations for fuel burnup, activation of structural materials, severe accident analysis, etc.

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