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Daido, Hiroyuki
Reza Kenkyu, 31(11), p.696 - 697, 2003/11
no abstracts in English
Daido, Hiroyuki
Reza Kenkyu, 31(11), p.698 - 706, 2003/11
no abstracts in English
Imamura, Toshiyuki; Muramatsu, Kazuhiro; Kitabata, Hideyuki*; Kaneko, Isamu*; Yamagishi, Nobuhiro*; Hasegawa, Yukihiro*; Takemiya, Hiroshi*; Hirayama, Toshio
Joho Shori Gakkai Kenkyu Hokoku 2001-ARC-142, p.49 - 54, 2001/03
no abstracts in English
Sawamura, Sadashi*
PNC TJ1600 94-002, 61 Pages, 1994/02
None
Nihon Genshiryoku Gakkai-Shi, 35(7), p.596 - 599, 1993/07
no abstracts in English
Sunaga, Hiromi
Radioisotopes, 41(3), p.75 - 76, 1992/00
no abstracts in English
; Kubota, Masumitsu; *; *
JAERI-M 91-147, 191 Pages, 1991/09
no abstracts in English
Umezawa, Hirokazu
Nihon Genshiryoku Gakkai-Shi, 32(7), p.658 - 660, 1990/07
no abstracts in English
Sunaga, Hiromi; Tanaka, Susumu; ; Agematsu, Takashi; Yotsumoto, Keiichi; Tanaka, Ryuichi; Yoshida, Kenzo; *; *; *; et al.
JAERI-M 89-182, 31 Pages, 1989/11
no abstracts in English
; ;
JAERI-M 8810, 37 Pages, 1980/04
no abstracts in English
; ; ; Machi, Sueo
JAERI-M 7496, 37 Pages, 1978/01
no abstracts in English
Au Grain for Medical Use; ; ; Genka, Tsuguo
JAERI-M 7209, 14 Pages, 1977/08
no abstracts in English
Gosei Jushi, 18(11-12), p.16 - 20,10, 1972/11
no abstracts in English
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.
Okumura, Keisuke; Sato, Wakaei; Maeda, Hirobumi; Wakaida, Ikuo; Washiya, Tadahiro; Katakura, Junichi*
no journal, ,
In order to develop the evaluation technology of the most probable radiation source and dose rate distributions in the primary containment vessel (PCV), we evaluated the radiation source distribution based on the results of fuel burn-up calculation, activation calculation of structural materials and severe accident analysis. Then, we built a three-dimensional PCV model for the particle transport Monte Carlo calculation code PHITS. From the PHITS calculation, we obtained the response function of the dose rate distribution due to each unit radiation source.
Takahashi, Tone; Koizumi, Mitsuo; Tomikawa, Hirofumi; Kimura, Yoshiki; Sato, Yuki; Terasaka, Yuta; Torii, Tatsuo; Yamanishi, Hirokuni*; Wakabayashi, Genichiro*
no journal, ,
no abstracts in English
Machida, Masahiko
no journal, ,
no abstracts in English
Machida, Masahiko
no journal, ,
no abstracts in English
Machida, Masahiko
no journal, ,
no abstracts in English
Shi, W.*; Machida, Masahiko; Yamada, Susumu; Yoshida, Toru*; Hasegawa, Yukihiro*; Okamoto, Koji
no journal, ,
