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JAEA Reports

Annual technical report of the prototype fast breeder reactor Monju; 2013

Fast Breeder Reactor Research and Development Center, Tsuruga Head Office

JAEA-Review 2014-030, 138 Pages, 2014/08

JAEA-Review-2014-030.pdf:71.69MB

The prototype fast breeder reactor Monju has accumulated technical achievements in order to establish the fast breeder reactor cycle technology in Japan using the operation and maintenance experience, etc. This annual report summarizes the primary achievements and the data related to the plant management in Monju during fiscal 2013.

JAEA Reports

None

; *; *; ;

JNC TN8440 2000-001, 126 Pages, 1999/03

JNC-TN8440-2000-001.pdf:4.37MB

None

JAEA Reports

PNC Technical Review No.104

PNC TN1340 97-004, 170 Pages, 1997/12

PNC-TN1340-97-004.pdf:26.83MB

no abstracts in English

JAEA Reports

Preliminary design study of a steady state tokamak device

Miya, Naoyuki; *; Ushigusa, Kenkichi; Oikawa, Akira; Imai, Tsuyoshi; ; Nishitani, Takeo; Matsuzaki, Yoshimi; Kuriyama, Masaaki;

JAERI-M 92-140, 156 Pages, 1992/09

JAERI-M-92-140.pdf:4.19MB

no abstracts in English

Oral presentation

Development of welding tool for remote maintenance of ITER blanket

Tanigawa, Hisashi; Ueno, Kenichi; Inoue, Ryuichi; Takeda, Nobukazu; Kakudate, Satoshi

no journal, , 

The shield blanket in ITER has an active cooling structure necessitating hydraulic connections to the cooling water manifold. To maintain or replace the blanket, welding the hydraulic connection by remote handling is necessary. Access for the welding is limited in a small hole in the first wall because of spatial constraints related to neutron and heat fluxes. A bore welding tool is required. Laser and TIG welding tools have been developed, and the welding conditions have been optimized for all position welding to horizontally located pipes. Additionally capability of re-welding between as-cut and new pipes has been confirmed. Based on the results, applicability of laser and TIG welding are comparatively assessed.

Oral presentation

Development of a recover device for loose parts in liquid sodium; Basic test of the recovery mechanism unit

Ishiguro, Takahiro; Hattori, Shushi*; Hattori, Tsukasa*; Shirahama, Takuma*; Ueda, Masashi

no journal, , 

In sodium cooled fast-reactors, opaque and highly chemical reactive sodium is used as coolant. Therefore, in the event of a loose part (dropped part) occurring, it is difficult to search and recover them under liquid sodium, potentially stopping the plant operation for a long time. The paper presents a prototype of the recovery mechanism, which is an important component of recover device for loose parts, and reports measurements and testing of it in liquid sodium.

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