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Sakamoto, Masahiro; Okumura, Keisuke; Kanno, Ikuo; Matsumura, Taichi; Terashima, Kenichi; Riyana, E. S.; Mizokami, Masato*; Mizokami, Shinya*
JAEA-Research 2024-017, 14 Pages, 2025/03
JAEA-Research-2024-017.pdf:1.34MB
In the TEPCO's Fukushima Daiichi Nuclear Power Station (1F), a trial retrieval of fuel debris with small-amount from Unit 2 is planned. The retrieved fuel debris will be transported out of 1F to Institutes in Ibaraki prefecture for analysis. The analyzed results will be utilized for the improvement of the processes (retrieval, transportation and storage) in the fuel debris management as feedback, and also for the development of technologies necessary in the future. The weight of fuel debris in the trial retrieval is planned to be a few grams. After the trial, the scale of retrieval will be expanded step by step. In the trial retrieval, a rational transportation container should be considered beforehand, according to the laws and regulations associated with the off-site transportation. The transportation container has a classification and the classification is decided according to the radioactivity of the material in the container. In this report, we evaluated the applicability of the Type A transport container to contribute to the safety assessment of retrieved fuel debris.
Shimazaki, Yosuke; Sawahata, Hiroaki; Yanagida, Yoshinori; Shinohara, Masanori; Kawamoto, Taiki; Takada, Shoji
JAEA-Technology 2016-038, 36 Pages, 2017/02
JAEA-Technology-2016-038.pdf:8.75MB
The High Temperature Engineering Test Reactor (HTTR) has three neutron startup sources (NSs) in the reactor core, each of which consists of 
Cf with 3.7GBq The NSs are exchanged at the interval of approximately 7 years. The NS holders including NSs are transported from the dealer's hot cell to the reactor facility of HTTR using a transportation container. The loading work of NS holders to the Control Rod guide blocks is subsequently carried out in the fuel handling machine maintenance pit of HTTR. Following technical issues were extracted from the experiences in the past two exchange works of NSs to develop a safety handling procedure; (1) The reduction and prevention of radiation exposure of workers. (2) The exclusion of falling of NS holder. Then, a new transportation container special to the NSs of HTTR was developed to solve the technical issues while keeping the cost as low as that for overhaul of conventional container and satisfying the regulation of A type transportation package.
Nomura, Yasushi; Murazaki, Minoru*; Okuno, Hiroshi
JAERI-Data/Code 2001-029, 120 Pages, 2001/11
JAERI-Data-Code-2001-029.pdf:6.16MB
no abstracts in English
Ohira, Shigeru; Suzuki, Takumi; ; Nishi, Masataka
Fusion Engineering and Design, 45(2), p.187 - 195, 1999/00
Times Cited Count：4 Percentile：34.34(Nuclear Science & Technology)no abstracts in English
Kato, Mineo; Kurosawa, Kiyoyuki; Sugai, Hiroyuki; Tanase, Masakazu; Matsuzaki, Teiichiro*; Ishida, Katsuhiko*; Nagamine, Kanetada*
KEK Proceedings 99-11, p.113 - 127, 1999/00
no abstracts in English
Ohira, Shigeru
Purazuma, Kaku Yugo Gakkai-Shi, 73(8), p.764 - 766, 1997/08
no abstracts in English
Okuno, Kenji; Konishi, Satoshi; Yamanishi, Toshihiko; Ohira, Shigeru; Enoeda, Mikio; Nakamura, Hirofumi; Iwai, Yasunori; Hayashi, Takumi; Kawamura, Yoshinori; Kobayashi, Kazuhiro
Fusion Technology 1996, p.1277 - 1280, 1997/00
no abstracts in English
Miyazawa, Masataka; Itabashi, Yukio; ; ; ; ; ; Oyamada, Rokuro;
9th Int. Symp. on Packaging and Transportation of Radioactive Materials, Vol. 3, p.1686 - 1693, 1989/00
no abstracts in English
Yagawa, Genki*;
JAERI-M 87-165, 168 Pages, 1987/10
no abstracts in English
Yagawa, Genki*;
JAERI-M 87-156, 312 Pages, 1987/10
no abstracts in English
Yanagisawa, Hiroshi; Suzaki, Takenori; Nitta, Kazuo
Proc.Int.Seminar on Nuclear Criticality Safety, p.84 - 88, 1987/00
no abstracts in English
;
Transactions of the American Nuclear Society, 43, p.729 - 730, 1982/00
no abstracts in English
; ; ; ; ; ; ; Wadachi, Yoshiki; Araki, Kunio;
JAERI-M 9263, 22 Pages, 1981/01
no abstracts in English
; ; ; ; ; ;
JAERI-M 8752, 43 Pages, 1980/03
no abstracts in English
Sawai, Sadamu
Nihon Genshiryoku Gakkai-Shi, 7(3), p.167 - 168, 1965/00
no abstracts in English
Shimazaki, Yosuke; Sawahata, Hiroaki; Yanagida, Yoshinori; Shinohara, Masanori; Kawamoto, Taiki; Takada, Shoji
no journal, ,
In High Temperature Engineering Test Reactor (HTTR), three neutron holders containing Cf with 3.7GBq for each are loaded in the graphite blocks and inserted into the reactor core as a neutron startup source (NS) which is changed at the interval of approximately 7 years. These neutron holders containing the neutron sources are transported from the dealer's hot cell to HTTR using the transportation container. The holders loading to the graphite block are carried out in the fuel handling machine maintenance pit of HTTR. Technical issues were recognized for the transportation container in the past two exchange works for the safety handling work of NS holder. On the other hand, it was required that an overhaul of the conventional transportation container or development of a new transportation container because the conventional transportation container was manufactured about twenty years ago. Therefore, the development of a new transportation container for NSs, which can solve these technical issues with low cost, was carried out.
Shimazaki, Yosuke; Sawahata, Hiroaki; Yanagida, Yoshinori; Shinohara, Masanori; Kawamoto, Taiki; Takada, Shoji
no journal, ,
In High Temperature Engineering Test Reactor (HTTR), three neutron holders containing Cf with 3.7 GBq for each are loaded in the graphite blocks and inserted into the reactor core as a neutron startup source (NS) which is changed at the interval of approximately 7 years. These neutron holders containing the neutron sources are transported from the dealer's hot cell to HTTR using the transportation container. The holders loading to the graphite block are carried out in the fuel handling machine maintenance pit of HTTR. Technical issues were recognized for the transportation container in the past two exchange works for the safety handling work of NS holder. On the other hand, it was required that an overhaul of the conventional transportation container or development of a new transportation container because the conventional transportation container was manufactured about twenty years ago. Therefore, the development of a new transportation container for NSs, which can solve these technical issues with low cost, was carried out. Radiation exposure dose of workers was reduced. As the result, it was confirmed that the NS handling work was improved by new transportation container.
