Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Saegusa, Jun; Tagawa, Akihiro; Kurikami, Hiroshi; Iijima, Kazuki; Yoshikawa, Hideki; Tokizawa, Takayuki; Nakayama, Shinichi; Ishida, Junichiro
Mechanical Engineering Journal (Internet), 3(3), p.15-00609_1 - 15-00609_7, 2016/06
After the Fukushima nuclear accident, JAEA lead off demonstration tests to find out effective decontamination methods for various school facilities in Fukushima. It included (1) dose reduction measures at schoolyards, (2) purification of swimming pool water and (3) removal of surface contamination of playground equipments. Through these tests, they established practical methods suitable for each situation; (1) At school yards, dose rates were drastically reduced by removing topsoil which was then placed in trenches of 1 m deep; (2) For the purification of pool water, the flocculation-coagulation treatment was found to be effective for collecting radiocesium dissolved in the water; (3) Demonstration tests for playground equipments, such as horizontal bars and a sandbox wood frame, suggested that effectiveness of decontamination considerably varied depending on the material, paint or coating condition. This paper reviews these demonstrations.
Saegusa, Jun; Tagawa, Akihiro; Kurikami, Hiroshi; Iijima, Kazuki; Yoshikawa, Hideki; Tokizawa, Takayuki; Nakayama, Shinichi; Ishida, Junichiro
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 5 Pages, 2015/05
After the Fukushima nuclear accident, JAEA lead off demonstration tests to find out effective decontamination methods for various school facilities in Fukushima. It included (1) dose reduction measures at schoolyards, (2) purification of swimming pool water and (3) removal of surface contamination of playground equipments. Through these tests, they established practical methods suitable for each situation; (1) At school yards, dose rates were drastically reduced by removing topsoil which was then placed in trenches of 1 m deep; (2) For the purification of pool water, the flocculation-coagulation treatment was found to be effective for collecting radiocesium dissolved in the water; (3) Demonstration tests for playground equipments, such as horizontal bars and a sandbox wood frame, suggested that effectiveness of decontamination considerably varied depending on the material, paint or coating condition. This paper reviews these demonstrations.
Department of HTTR Project
JAERI-Review 2005-010, 83 Pages, 2005/03
JAERI-Review-2005-010.pdf:5.18MB
The HTTR (High Teperature Engineering Test Reactor) with the thermal power of 30MW and the reactor outlet coolant temperature of 850/950
C is the first high temperature gas-cooled reactor (HTGR) in Japan, which uses coated fuel particle, graphite for core components and helium gas for primary coolant. December 2001, the thermal power of 30MW and the reactor outlet coolant temperature of 850C was attained. JAERI received the certificate of pre-operation test, that is, the commissioning licence for the HTTR in March 2002. This report summarizes operation, tests, maintenance, radiation control, and construction of components and facilities for the HTTR as well as R&D on HTGRs for FY2003.
Takamatsu, Kuniyoshi; Nakagawa, Shigeaki
Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(4), p.369 - 380, 2004/12
This paper describes the validation of the TAC-NC code using the measured value of the test by tripping of one and two out of three gas circulators at 30% (9MW). By upgrading the code, the analytical result can evaluate accurately the measured value of the transient temperature distribution within 20C. Also, the improved code can analyze the maximum fuel temperature and temperature distributions of the test by tripping all the three gas circulators. The result of this study can be applied to development for not only the commercial HTGRs but also the Very High Temperature Reactor (VHTR) such as one of the Generation IV reactors.
Oba, Toshihiro; Yanagihara, Takao; Kato, Chiaki; Hamada, Shozo
JAERI-Tech 2001-059, 36 Pages, 2001/09
The demonstration test for evaluating reliability of the acid recovery evaporator at Rokkasho Reprocessing Plant has been carried out at JAERI. For the nondestructive mesurement of the thickness of heat transfer tubes in the acid recovery evaporator and short tubes used in corrosion test, we have developed ultra sonic thickness measuring apparatus using immersion method with high resolution. This apparatus can measure and record tube thickness automatically with a personal computer. The results obtained by this apparatus are coincident with the results obtained by a destructive method using an optical microscope.
Kaminaga, Masanori; Sasaki, Shinobu; Haga, Katsuhiro; Aso, Tomokazu; Kinoshita, Hidetaka; Kogawa, Hiroyuki; Akimoto, Atsushi*; Adachi, Junichi*; Hino, Ryutaro
JAERI-Tech 2000-060, 37 Pages, 2000/11
JAERI-Tech-2000-060.pdf:5.54MB
no abstracts in English
Ito, Takao; Yamazaki, Haruyuki*; Usui, Katsutomi; Mogaki, Kazuhiko; Kuriyama, Masaaki
JAERI-Tech 99-066, p.13 - 0, 1999/09
no abstracts in English
Haga, Katsuhiro; *; Inagaki, Yoshiyuki; Hayashi, Koji; Ogawa, Masuro
JAERI-Tech 99-062, 31 Pages, 1999/08
no abstracts in English
Hada, Kazuhiko; Fujisaki, Katsuo; *; Shibata, Taiju; Inagaki, Yoshiyuki; Hino, Ryutaro
JAERI-Tech 97-004, 113 Pages, 1997/02
no abstracts in English
Takada, Junichi; Suzuki, Motoe; Tsukamoto, Michio; Koike, Tadao; *
JAERI-Tech 96-054, 237 Pages, 1996/12
no abstracts in English
JAERI-Data/Code 96-026, 108 Pages, 1996/09
JAERI-Data-Code-96-026.pdf:5.34MB
no abstracts in English
Nakamura, Naohiko; Hashimoto, Kazuichiro; Maruyama, Yu; Igarashi, Minoru*; Hidaka, Akihide; Sugimoto, Jun
Proc. of ASME
JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 3, p.199 - 203, 1996/00
no abstracts in English
Hino, Ryutaro; Suzuki, Kunihiro; Haga, Katsuhiro; Nekoya, Shinichi; Fukaya, Kiyoshi; Shimizu, Saburo; Onuki, Kaoru; Takada, Shoji; Mogi, Haruyoshi; Sudo, Yukio
JAERI-Review 95-016, 115 Pages, 1995/10
no abstracts in English
*; *; Tokunaga, Okihiro; Hashimoto, Shoji; Namba, Hideki; *; *
Denki Hyoron, 0(8), p.70 - 73, 1995/08
no abstracts in English
Enoeda, Mikio; Yamanishi, Toshihiko; Yamada, Masayuki; Konishi, Satoshi; Okuno, Kenji; Willms, R. S.*; Taylor, D.*; W.Harbin*; Bartlit, J. R.*; Anderson, J. L.*
JAERI-Research 95-034, 29 Pages, 1995/05
JAERI-Research-95-034.pdf:0.99MB
no abstracts in English
Takada, Junichi; Suzuki, Motoe; Tsukamoto, Michio; Koike, Tadao; Nishio, Gunji
JAERI-Tech 95-024, 339 Pages, 1995/03
no abstracts in English
; Hino, Ryutaro; Inagaki, Yoshiyuki; Takase, Kazuyuki; Ioka, Ikuo; Takada, Shoji; Suzuki, Kunihiro; Kunitomi, Kazuhiko; Maruyama, So;
JAERI 1333, 196 Pages, 1995/03
no abstracts in English
Matsumoto, Kiyoshi; Muramatsu, Ken; *; *
The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1385 - 1392, 1995/00
no abstracts in English
Nishio, Gunji; *
Nuclear Technology, 102, p.232 - 251, 1993/05
Times Cited Count：3 Percentile：38.1(Nuclear Science & Technology)no abstracts in English
