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Ito, Kazuhiro; Tanabe, Hiromi; Kaneko, Yoshihisa; Kagota, Eiichi; Takahashi, Yasuo
Proceedings of 2013 International Congress on Advances in Nuclear Power Plants (ICAPP 2013) (USB Flash Drive), 10 Pages, 2013/04
The Monju is equipped with two types of hydrogen-meters to detect water leakage in steam generators. Since they are so highly-sensitive as to detect minor water leak from a steam generator tube, they sometimes detect hydrogen concentration increases at plant operational condition changes such as start-up without any water leak. No water leak was experienced during one year operation of the Startup Test up to 40% in 1995, although hydrogen concentration sometimes increased at plant operational condition changes. The H behavior of Monju IHTS during the previous Startup Test was examined and the following knowledge was obtained: The in-sodium H behaves in parallel with the IHTS sodium temperature. In-cover-gas H behavior is more complicated and sensitive to plant operational condition changes such as plant load changes than the in-sodium one. Both types of H-meters underwent a certain degree of zero level drift during one year operation.
Kaito, Takeji; Otsuka, Satoshi; Inoue, Masaki; Asayama, Tai; Uwaba, Tomoyuki; Mizuta, Shunji; Ukai, Shigeharu*; Furukawa, Tomohiro; Ito, Chikara; Kagota, Eiichi; et al.
Journal of Nuclear Materials, 386-388, p.294 - 298, 2009/04
Times Cited Count：32 Percentile：88.55(Materials Science, Multidisciplinary)In order to examine irradiation effect on creep rupture strength of Oxide Dispersion Strengthened (ODS) steel claddings, the in-pile creep rupture test was conducted using Material Testing Rig with Temperature Control (MARICO)-2 in the experimental fast reactor JOYO. Fourteen creep rupture events were successfully detected by the temperature change in each capsule and the 
-ray spectrometry of the cover gas. Time to creep ruptures of six ODS steel specimens were identified by means of Laser Resonance Ionization Mass Spectrometry (RIMS), and no irradiation effect on creep rupture strength was confirmed within the irradiation condition in the MARICO-2 test.
Ito, Chikara; Kagota, Eiichi; Aoyama, Takafumi
Journal of Power and Energy Systems (Internet), 2(2), p.620 - 632, 2008/00
An in-pile creep rupture experiment was conducted in the experimental fast reactor Joyo to evaluate the creep rupture strength of oxide dispersion strengthened (ODS) ferritic steel under neutron irradiation. ODS has been developed as a most promising fuel cladding material for the next generation fast reactor because of its high temperature resistance and low swelling properties. The irradiation test device MAterial testing RIg with temperature COntrol (MARICO) was developed for the in-pile experiment in Joyo with a temperature control precision of 
4
C. Twenty four ODS specimens with no fuel were pressurized by helium gas up to 22 MPa to accelerate the creep rupture testing. The specimen temperature in the MARICO is controlled by changing the ratio of argon and helium fill gases, which changes the gas gap thermal conductivity between the double walled capsule containing the specimen. The experiment has been carried out in the Joyo MK-III core from April 2006 and will continue until May 2007. Each creep rupture event was successfully detected by the temperature change at the exit of the capsule and by -ray spectrometry of the reactor cover gas when the filled gas was released from the specimen. The specimen was then identified by analyzing the tag gas isotopic ratio using laser resonance ionization mass spectrometry (RIMS).
Ito, Chikara; Kagota, Eiichi; Ishida, Koichi; Kitamura, Ryoichi; Aoyama, Takafumi
Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 9 Pages, 2007/04
no abstracts in English
Kagota, Eiichi; Noguchi, Koichi; Kitamura, Ryoichi; Abe, Kazuyuki
no journal, ,
no abstracts in English
