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JAEA Reports

Development of safety management system for works in radiation controlled area (Joint research)

Hiyama, Kazuhisa; Hanawa, Nobuhiro; Kurosawa, Akihiko; Eguchi, Shohei; Hori, Naohiko; Kusunoki, Tsuyoshi; Ueda, Hisao; Shimada, Hiroshi; Kanda, Hiroaki*; Saito, Isamu*

JAEA-Technology 2013-045, 32 Pages, 2014/02


This report summarizes regarding to develop of real-time multifunctional access control system which is able to manage worker's access control and exposure dose at real-time in the reactor building, besides worker's location and worker might be fall down by accident.

JAEA Reports

The Outline of investigation on integrity of JMTR concrete structures, cooling system and utility facilities

Ebisawa, Hiroyuki; Hanakawa, Hiroki; Asano, Norikazu; Kusunoki, Hidehiko; Yanai, Tomohiro; Sato, Shinichi; Miyauchi, Masaru; Oto, Tsutomu; Kimura, Tadashi; Kawamata, Takanori; et al.

JAEA-Technology 2009-030, 165 Pages, 2009/07


The condition of facilities and machinery used continuously were investigated before the renewal work of JMTR on FY 2007. The subjects of investigation were reactor building, primary cooling system tanks, secondary cooling system piping and tower, emergency generator and so on. As the result, it was confirmed that some facilities and machinery were necessary to repair and others were used continuously for long term by maintaining on the long-term maintenance plan. JMTR is planed to renew by the result of this investigation.

Journal Articles

Experience on return of research reactor spent fuels in Japan

Sagawa, Hisashi; Koda, Nobuyuki; Hanawa, Nobuhiro; Maruo, Takeshi; Miyazawa, Masataka; Unesaki, Hironobu*; Nakagome, Yoshihiro*

IAEA-TECDOC-1593, p.121 - 128, 2008/06

In Japan, 1,712 of Research Reactor Spent Nuclear fuels (RRSNFs) have been transported to the US successfully since the receipt in accordance with the foreign research reactor spent nuclear fuel acceptance policy started in 1996. Especially, Japan Atomic Energy Agency (JAEA) carried out shipment to the US of eight times and of 1,283 fuel elements in total. This paper describes experiences of RRSNF transportation to the US in Japan.

JAEA Reports

Confirmation tests for fabrication of low density MOX pellet for FBR

Murakami, Tatsutoshi; Suzuki, Kiichi; Hatanaka, Nobuhiro; Hanawa, Yukio; Shinozaki, Masaru; Murakami, Shinichi; Tobita, Yoshimasa; Kawasaki, Takeshi; Kobayashi, Yoshihito; Iimura, Naoto; et al.

JAEA-Technology 2008-017, 97 Pages, 2008/03


Low density MOX pellets for FBR "MONJU" have not been fabricated in Plutonium Fuel Fabricating Facility (PFPF) for these 9 years since completion of the first reload fuel for "MONJU" in 1995. In this period, about 60 % of machines in the pellet fabrication process of PFPF have been replaced with new ones, and fabrication of MOX pellets for "JOYO" has been continued using these machines. Concerning the feed MOX powders for "MONJU", the amount of decay heat has been increased with increase of accumulated Am-241 in this period. In addition, powder characteristic of recycled MOX powder which is one of feed powders, MH-MOX powder, UO$$_{2}$$ powder and recycled MOX powder, was significantly changed by replacing former processing machine used for scrap recycling with improved one. Using MOX powder with increased decay heat and recycled MOX powder processed by new machine, a series of low density MOX pellet fabrication tests were conducted to confirm pellet fabrication conditions for current pellet fabrication machines from October in 2004 to August in 2006. As a conclusion, it was confirmed that low density MOX pellets could be fabricated using these feed powders and replaced machines by adjusting pellet fabrication conditions adequately. This report summarizes the results of a series of low density MOX pellet fabrication tests.

Oral presentation

Current status and issues relative to LEU spent fuel of JMTR and JRR-3

Izumo, Hironobu; Hanawa, Nobuhiro; Nagadomi, Hideki; Torii, Yoshiya; Inoue, Takeshi; Kawamura, Hiroshi

no journal, , 

The refurbishment works of JMTR had been completed as scheduled. The renewed JMTR operation is expected to start as soon as possible after check for earthquake effect etc, and will be utilized mainly for safety evaluation on LWRs and $$^{99}$$Mo production by without uranium target. JRR-3 has been used mainly for neutron beam experiments and radio isotope production. The number of LEU silicide spent fuels (SFs) stored at the reactor facilities in JAEA will increase in future by the JMTR restart. It will be one of the key issues to decrease the number of stored SFs for stable reactor operation. Consequently, it is thought that accomplishment of the FRRSNF acceptance program and its extension or alternative measures are very important.

Oral presentation

Real-time multi-function entry / exit management system

Hiyama, Kazuhisa; Kurosawa, Akihiko; Asano, Norikazu; Onoue, Ryuji; Eguchi, Shohei; Hanawa, Nobuhiro; Hori, Naohiko; Ueda, Hisao; Kanda, Hiroaki*

no journal, , 

In order to prevent radiation accident and its expansion, more integrated management system is required to safety management for radiation workers in the nuclear facilities. Therefore, JAEA (Japan Atomic Energy Agency) and HAM (Hitachi Aloka Medical, Ltd) have developed innovative real-time multi-function entry/exit management system which managed worker's exposed dose and position under the joint developed patent. This system is sharing worker's data among workers and server manager who is inside of or outside of building, such as worker's positing, health condition and exposed dose. It consists of mobile equipments, receivers, LAN, and servers system. This report summarizes the system to be installed in the JMTR.

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