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Okumura, Keisuke; Kojima, Kensuke; Hagura, Hiroyuki*; Ito, Takashi*; Miyoshi, Katsumasa*
no journal, ,
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.
Abe, Yuta; Yamashita, Takuya; Kawakami, Tomohiko*
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no abstracts in English
Okazaki, Kodai*; Kawakami, Tomohiko*; Abe, Yuta; Otaka, Masahiko
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no abstracts in English
Okazaki, Kodai*; Kawakami, Tomohiko*; Abe, Yuta; Otaka, Masahiko; Sato, Ikken
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no abstracts in English
Kurata, Masaki; Madokoro, Hiroshi; Okumura, Keisuke; Sato, Ikken; Mizokami, Masato*; Ito, Kenichi*; Mizokami, Shinya*
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Based on the analysis of the samples collected in the PCV interior of Fukushima Daiichi NPP, potential issues regarding the fuel debris retrieval are summarized. The analytical targets, analytical method and obtainable knowledge that are necessary to evaluate each issue are discussed. Valuable information can be obtained even from small samples to understand the current situation of the plant and the accident progression. Although the amount of collectable samples is limited, we considered how to evaluate the whole fuel debris and how to utilize the analytical results for recriticality, burnup and safety issues.
Matsuhira, Nobuto*; Komatsu, Ren*; Nakashima, Shinsuke*; Yamashita, Atsushi*; Fukui, Rui*; Takahashi, Hiroyuki*; Shimazoe, Kenji*; Woo, H.*; Tamura, Yusuke*; Takashi, Takayuki*; et al.
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Nakashima, Shinsuke*; Komatsu, Ren*; Alessandro, M.*; Angela, F.*; Woo, H.*; Kawabata, Kuniaki; Asama, Hajime*
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Suzuki, Masahiro; Yamaguchi, Takashi; Machida, Masahiko; Kawabata, Kuniaki; Ito, Rintaro
no journal, ,
In the decommissioning of the Fukushima Daiichi NPS (1F), prior to the full-scale implementation of fuel debris removal operations, it is necessary to improve the on-site environment in order to safely and efficiently construct access routes in the reactor building (R/B). Then, JAEA is now developing a prototype system that estimates radioactive source distributions by using on-site dose rate data and examines countermeasure effects of such as decontamination, shielding with estimated contamination (radiation sources) on the estimated sources in cyberspace. This report presents overview of the development project and its current status.
Suzuki, Masahiro; Machida, Masahiko; Ito, Rintaro; Kawabata, Kuniaki; Yamaguchi, Takashi; Okamoto, Koji
no journal, ,
no abstracts in English
Suzuki, Masahiro; Machida, Masahiko; Yamaguchi, Takashi; Miyamura, Hiroko; Yamada, Susumu; Okamoto, Koji; Hasegawa, Yukihiro*; Yoshida, Toru*; Wei, S.*
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