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JAEA Reports

Investigation of the crack in a reflector element of JRR-4

The ad hoc Working Group of Investigating into the Crack on a Reflector Element of JRR-4

JAEA-Technology 2008-070, 121 Pages, 2008/09

JAEA-Technology-2008-070(errata).pdf:0.06MB
JAEA-Technology-2008-070-1.pdf:40.24MB
JAEA-Technology-2008-070-2.pdf:56.57MB

A crack was ascertained on a weld area of one reflector element on December 28, 2007. The Department of Research Reactor and Tandem Accelerator set up an ad hoc working group of experts in the JAEA, and investigated cause of crack on the weld area. The following examinations were carried out; visual examination, dimensional examination, fractography examination and so on. It was concluded that the main cause of the crack is the swelling of graphite in the reflector element. The swelling must be due to neutron irradiation. We carried out a radiografical examination of the other reflector elements. As the result, we determined that many of them were not in a suitable state to be used because of swelling of graphite. The design of the new reflector elements should be carried out, based on the relation between the irradiation dose and swelling rate, which has been obtained in these investigation.

JAEA Reports

Preventive measures for the recurrence of control rod insertion failure in Japan Research Reactor No.4 (JRR-4)

JRR-4 Operation Division; Research Reactor Utilization Division

JAERI-Tech 2005-042, 58 Pages, 2005/07

JAERI-Tech-2005-042.pdf:5.4MB

Japan Research Reactor No.4 (JRR-4) was shut down manually, due to the control rod insertion failure occurred during the rated power (3,500kW) operation on June 10, 2005. It became evident by the investigation that a screw bolt at the control rod support got loose and blocked the control rod insertion. The failure was recovered through replacement with the new screw bolt. Considering the importance of this event, we decided to inspect all screw bolts over the core that may cause a control rod insertion failure. Furthermore, we decided to carry out periodical inspection about these screw bolts whether they were tightened enough or not. This report describes the result of inspection carried out as the preventive measures.

JAEA Reports

Characteristic experiments for JRR-3M silicide core

JRR-3 Operation Division; Research Reactor Utilization Division

JAERI-Tech 2000-027, p.194 - 0, 2000/03

JAERI-Tech-2000-027.pdf:8.47MB

no abstracts in English

JAEA Reports

Experiences on operation, maintenance and utilization in JRR-2

JRR-2 Operations Office

JAERI-Tech 94-014, 279 Pages, 1994/08

JAERI-Tech-94-014.pdf:11.08MB

no abstracts in English

JAEA Reports

The First loading fuel elements and power-up for JRR-2

JRR-2 Control Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Kohayakawa, Toru; Morozumi, Minoru; Kambayashi, Yuichiro; Shitomi, Hajimu; Kokanezawa, Takashi; et al.

JAERI 1027, 57 Pages, 1962/09

JAERI-1027.pdf:4.76MB

no abstracts in English

JAEA Reports

Treatment and analysis of the water and gas in JRR-2

JRR-2 Operations Office; Kambara, Toyozo; Shoda, Katsuhiko; Hirata, Yutaka; Shoji, Tsutomu; Haginoya, Kinichi; Kohayakawa, Toru; Yamaki, Jikei; Yokota, Mitsuo; Horiki, Oichiro; et al.

JAERI 1024, 79 Pages, 1962/08

JAERI-1024.pdf:5.66MB

no abstracts in English

JAEA Reports

Leak test of the JRR-2 housing building

JRR-2 Operations Office; Kambara, Toyozo; Sakata, Hajime; Sawai, Sadamu; Kaneko, Minoru; Endo, Yuzo; Kitahara, Tanemichi; Oyamada, Rokuro; Iwashita, Akira; Kasahara, Yuko

JAERI 1018, 12 Pages, 1962/07

JAERI-1018.pdf:0.77MB

no abstracts in English

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