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Fujiwara, Kazushige*; Ito, Masanobu*; Sasanuma, Miwa*; Tanaka, Hideo*; Hirotani, Kiyoshi*; Onizawa, Kunio; Suzuki, Masahide; Amezawa, Hiroo*
Transactions of the 20th International Conference on Structural Mechanics in Reactor Technology (SMiRT-20) (CD-ROM), 8 Pages, 2009/08
Concerns over aged nuclear power stations are mounting in Japan today. However, there exists only a small number of experimental studies regarding the effect of radiation exposure to concrete. We have consequently conducted an irradiation test at JMTR on concrete specimens to confirm the effect of radiation exposure on the basic material properties of concrete. Irradiation temperature was kept lower than 65
C. The maximum fast neutron fluence reached 12
10
n/cm
(E
0.1 MeV), which is sufficiently exceeding total fast neutron fluence to be exposed to the concrete located at the exterior of a reactor pressure vessel in a typical BWR for 60-year operation. Compressive strength of the irradiated concrete specimens was roughly equivalent to that of concrete specimens cured for the same duration under the standard environment. By measuring chemically bound water content of irradiated specimens, no changes after irradiation were observed. It was confirmed that radiation exposure did not significantly affect the basic material properties of concrete within the range of radiation doses adopted in this study.
Yachi, Shigeyasu; Sato, Tadashi; Suga, Shinichi*; Komuro, Yuichi; Uchida, Masaaki; Nakajima, Kunihisa; Nakamura, Jinichi; Amezawa, Hiroo; Omura, Hideaki*; Minato, Kazuo; et al.
JAERI-Review 2003-025, 162 Pages, 2003/09
JAERI-Review-2003-025.pdf:5.96MB
The report contains example of answers to the Problems of 31st(1999) to 35th(2003) Examinations for the Chief Engineer of Nuclear Fuel which were conducted as a national qualification examination. Brief explanations or references are given to some answers.
Saito, Shigeru; Fukaya, Kiyoshi*; Ishiyama, Shintaro; Amezawa, Hiroo; Yonekawa, Minoru; Takada, Fumiki; Kato, Yoshiaki; Takeda, Takashi; Takahashi, Hiroyuki*; Nakahira, Masataka
Journal of Nuclear Materials, 307-311(Part2), p.1573 - 1577, 2002/12
Times Cited Count：2 Percentile：16.38(Materials Science, Multidisciplinary)no abstracts in English
Komori, Yoshihiro; Amezawa, Hiroo; Komukai, Bunsaku; Narui, Minoru*; Konashi, Kenji*
KAERI/GP-195/2002, p.3 - 10, 2002/00
The actinide-hydride(UTh
Zr
H
) fuel has been studied for transmutation of long-lived actinide contained in the high level wastes and the first irradiation test was successfully carried out in the Japan Materials Testing Reactor (JMTR) of JAERI. Fuel pellets were fabricated by alloying and hydrogenation within an expected diameter error. The fuel pellets were designed to be irradiated below 873K on the fuel surface in consideration of hydrogen dissociation. Irradiation temperature was well agreed with designed value. Fuel burnup reached 0.2%FIMA for two JMTR operation cycles.
Saito, Shigeru; Fukaya, Kiyoshi; Ishiyama, Shintaro; Amezawa, Hiroo; Yonekawa, Minoru; Takada, Fumiki; Kato, Yoshiaki; Takeda, Takashi; Takahashi, Hiroyuki*; Koizumi, Koichi
JAERI-Tech 2001-035, 81 Pages, 2001/06
JAERI-Tech-2001-035.pdf:18.91MB
no abstracts in English
Takeyama, Tomonori; Chiba, Masaaki; Isozaki, Futoshi*; Amezawa, Hiroo; Itabashi, Yukio; Kikuchi, Taiji; Otabe, Yoshikiyo*; Hirata, Yuji*; Taka, Isamu; Oba, Toshihiro
JAERI-Tech 2001-024, 32 Pages, 2001/03
JAERI-Tech-2001-024.pdf:4.41MB
no abstracts in English
Kurata, Yuji; Itabashi, Yukio; Mimura, Hideaki*; Kikuchi, Taiji; Amezawa, Hiroo; Shimakawa, Satoshi; Tsuji, Hirokazu; Shindo, Masami
Journal of Nuclear Materials, 283-287(Part.1), p.386 - 390, 2000/12
Times Cited Count：6 Percentile：41.99(Materials Science, Multidisciplinary)no abstracts in English
Sozawa, Shizuo; Amezawa, Hiroo*; Sampei, Shinichi; Tsuchiya, Bun*; Narui, Minoru*; Konashi, Kenji*
no journal, ,
no abstracts in English
