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JAEA Reports

Development of transportation container for neutron startup source of High Temperature Engineering Test Reactor (HTTR)

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 $$^{252}$$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.

JAEA Reports

Preparation of data relevant to "equivalent uniform burnup" and "equivalent initial enrichment" for burnup credit evaluation

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

Journal Articles

Design study of a tritium transport package for future fusion reactors

Ohira, Shigeru; Suzuki, Takumi; *; Nishi, Masataka

Fusion Engineering and Design, 45(2), p.187 - 195, 1999/00

 Times Cited Count:3 Percentile:69.65

no abstracts in English

Journal Articles

High purity tritium gas supplied by JAERI for muon catalyzed fusion research at RIKEN-RAL muon facilty

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

Journal Articles

Procurement of tritium for fusion reactor, 2; Transportation of large amounts of tritium for fusion reactors

Ohira, Shigeru

Purazuma, Kaku Yugo Gakkai-Shi, 73(8), p.764 - 766, 1997/08

no abstracts in English

Journal Articles

Tritium technology research and development at the tritium process laboratory of JAERI

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

Journal Articles

Drop test I.II and thermal test of full scale spent fuel shipping cask for a research reactor JMTR

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

JAEA Reports

Investigation on structgural analysis computer program of spent nuclear fuel shipping cask,II

Yagawa, Genki*;

JAERI-M 87-165, 168 Pages, 1987/10

JAERI-M-87-165.pdf:4.04MB

no abstracts in English

JAEA Reports

Investigation on structural analysis computer program of spent nuclear fuel shipping cask

Yagawa, Genki*;

JAERI-M 87-156, 312 Pages, 1987/10

JAERI-M-87-156.pdf:6.95MB

no abstracts in English

Journal Articles

Measurements of critical masses of non-uniform fuel rod lattice configulations

Yanagisawa, Hiroshi; Suzaki, Takenori; Nitta, Kazuo

Proc.Int.Seminar on Nuclear Criticality Safety, p.84 - 88, 1987/00

no abstracts in English

Journal Articles

Current status of the JMTR Hot Laboratory

;

Transactions of the American Nuclear Society, 43, p.729 - 730, 1982/00

no abstracts in English

JAEA Reports

Safety Assessment of PIC Container Used for Radioactive Wastes; Application Tests of PIC Container to Plastic Solidified Wastes

*; ; *; *; ; *; *; Wadachi, Yoshiki; ;

JAERI-M 9263, 22 Pages, 1981/01

JAERI-M-9263.pdf:1.18MB

no abstracts in English

JAEA Reports

Transportation and Safety Test of Type B(M) Packages for Radioisotopes

; ; ; ; ; ;

JAERI-M 8752, 43 Pages, 1980/03

JAERI-M-8752.pdf:2.13MB

no abstracts in English

Journal Articles

Problems of spent fuel transporting container

Sawai, Sadamu

Nippon Genshiryoku Gakkai-Shi, 7(3), p.167 - 168, 1965/00

no abstracts in English

Oral presentation

Development of new transportation container for neutron startup source of High Temperature Engineering Test Reactor

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 $$^{252}$$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.

Oral presentation

Improvement of neutron startup source (NS) handling work by developing a new transportation container for the NS of High Temperature Engineering Test Reactor (HTTR)

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 $$^{252}$$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.

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