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JAEA Reports

Immersion test in artificial water and evaluation of strength property on fuel cladding tubes irradiated in Fugen Nuclear Power Plant

Yamagata, Ichiro; Hayashi, Takehiro; Mashiko, Shinichi*; Sasaki, Shinji; Inoue, Masaki; Yamashita, Shinichiro; Maeda, Koji

JAEA-Testing 2013-004, 23 Pages, 2013/11

JAEA-Testing-2013-004.pdf:8.59MB

In the accident of the Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Co. accompanying the Great East Japan Earthquake, fuel assemblies kept in the spent fuel pool of reactor units 1-4, were exposed to the inconceivable environment such as falling and mixing of rubble, especially seawater were injected into unit 2-4. In order to evaluate the integrity of the fuel assemblies in spent fuel pools, and in the long-term storage after transported to the common storage pool, the immersion tests were performed using zircaloy-2 fuel cladding tubes irradiated in the advanced thermal reactor Fugen. The immersion liquid was prepared with doubling dilution of artificial seawater, which temperature was 80 $$^{circ}$$C and immersion time was about 336 hours, as assuming the situation of the pool. The results indicated zircaloy-2 cladding tubes had no significant corrosion and no influence on mechanical property by immersion tests with artificial seawater conditions of this work.

Journal Articles

Development of a YAG laser system for the edge Thomson scattering system in ITER

Hatae, Takaki; Yatsuka, Eiichi; Hayashi, Toshimitsu; Yoshida, Hidetsugu*; Ono, Takehiro; Kusama, Yoshinori

Review of Scientific Instruments, 83(10), p.10E344_1 - 10E344_3, 2012/10

 Times Cited Count:11 Percentile:51.68(Instruments & Instrumentation)

A prototype YAG laser system for the edge Thomson scattering system in ITER has been newly developed. Performance of the laser amplifier was improved by using flow tubes made of samarium-doped glass; the small signal gain reached 20 at its maximum. As a result, an output energy of 7.66 J at 100 Hz was successfully achieved, and the performance exceeded the target performance (5 J, 100 Hz).

Journal Articles

Decontamination experiment for floor of Fukushima Daiichi reactor building

Kanayama, Fumihiko; Hayashi, Takehiro; Kawatsuma, Shinji

Proceedings of American Nuclear Society Embedded Topical on Decommissioning, Decontamination and Reutilization and Technology Expo (DD&R 2012) (DVD-ROM), p.14 - 15, 2012/06

no abstracts in English

Journal Articles

Development of prototype YAG laser amplifier for the edge Thomson scattering system in ITER

Hatae, Takaki; Hayashi, Toshimitsu; Yatsuka, Eiichi; Kajita, Shin*; Yoshida, Hidetsugu*; Fujita, Hisanori*; Nakatsuka, Masahiro*; Yahagi, Kenichi*; Shinobu, Katsuya*; Ono, Takehiro; et al.

Journal of Plasma and Fusion Research SERIES, Vol.9, p.253 - 258, 2010/08

Journal Articles

Separation factor of americium from cerium in molten chloride-liquid gallium reductive extraction system

Toda, Taro*; Maruyama, Takehiro*; Moritani, Kimikazu*; Moriyama, Hirotake*; Hayashi, Hirokazu

Denki Kagaku Oyobi Kogyo Butsuri Kagaku, 77(8), p.649 - 651, 2009/08

 Times Cited Count:7 Percentile:18.65(Electrochemistry)

The distribution coefficients of Am and Ce were measured in the eutectic LiCl-KCl/liquid Ga system at 773K. By using ZrCl$$_4$$ as the oxide ion scavenger in order to avoid the formation of such oxychlorides as MO$$^{(n-2)+}$$, the effect of oxide ion concentration was well controlled on the distribution coefficients of Am and Ce. The separation factor between Am and Ce was then obtained to be about 100. By comparing the present value with the other experimental and the predicted ones, it was confirmed that the Ga system was more selective than the Bi and Cd system.

Journal Articles

Thermodynamic properties of lanthanides and actinides for reductive ectraction of minor actinides

Toda, Taro*; Maruyama, Takehiro*; Moritani, Kimikazu*; Moriyama, Hirotake*; Hayashi, Hirokazu

Journal of Nuclear Science and Technology, 46(1), p.18 - 25, 2009/01

 Times Cited Count:33 Percentile:91.29(Nuclear Science & Technology)

The excess thermodynamic quantities of lanthanides and actinides in molten salts and liquid metals were studied for reductive extraction of minor actinides. The excess enthalpies and entropies of those elements in the molten chloride phase were found to be correlated with the ionic radii of metal ions possibly due to complex formation. In the liquid metal phase, on the other hand, the excess enthalpies were explained with Miedema's atomistic model and the excess entropies were explained with the vibrational entropy due to alloy formation. Using these correlations and models, some missing values of the excess thermodynamic quantities were evaluated and the separation factors of minor actinides from lanthanides were calculated in different reductive extraction systems. The higher separation factors were obtained in the system using aluminum or gallium than in the system using bismuth or cadmium as the liquid metal phase.

Journal Articles

Reductive extraction of minor actinides from molten chloride into liquid gallium

Toda, Taro*; Maruyama, Takehiro*; Moritani, Kimikazu*; Moriyama, Hirotake*; Hayashi, Hirokazu

Proceedings of 2008 Joint Symposium on Molten Salts (USB Flash Drive), p.933 - 938, 2008/10

The distribution coefficients of Am and Ce were measured in the LiCl-KCl/Ga system at 773 K. By using ZrCl$$_4$$ as the oxide ion scavenger in order to avoid the formation of such oxychlorides as CeO$$^+$$ and AmO$$^+$$, the effect of oxide ion concentration was well controlled on the distribution coefficients of Am and Ce. The separation factor between Am and Ce was then obtained to be about 100. By comparing the present value with the other experimental and the predicted ones, it was confirmed that solvent metals were ordered from the most selective to the less selective one as Al$$>$$Ga$$>$$Bi$$>$$Cd.

Oral presentation

Development of YAG laser system for edge Thomson scattering diagnostics in ITER

Hatae, Takaki; Hayashi, Toshimitsu; Kajita, Shin*; Yoshida, Hidetsugu*; Fujita, Hisanori*; Nakatsuka, Masahiro*; Yahagi, Kenichi*; Shinobu, Katsuya*; Ono, Takehiro; Kusama, Yoshinori

no journal, , 

no abstracts in English

Oral presentation

Progress in ITER diagnostics development in Japan

Kawano, Yasunori; Kondoh, Takashi; Ishikawa, Masao; Hatae, Takaki; Hayashi, Toshimitsu; Ono, Takehiro; Ogawa, Hiroaki; Sugie, Tatsuo; Iwamae, Atsushi; Kusama, Yoshinori; et al.

no journal, , 

Progress in ITER diagnostics development in Japan is presented. (1) Micro Fission Chamber: A bending test of the mineral insulated cable has been carried out since its smallest bending radius would be 12 cm in the vacuum vessel. It has been confirmed that no damage has been observed even at the bending radius is small as 10 cm. (2) Thomson Scattering (Edge): It has been confirmed that the prototype YAG laser amplifier satisfies the target performance of ITER requirement. (3) Poloidal Polarimeter: Study of retro-reflectors in the first wall modules and the divertor cassette has been progressed. (4) Impurity Influx Monitor (Divertor): Mechanical designs of mirror box and optical shutter in the divertor cassette have been designed. (5) Upper Port Plug: For the generic design of the upper port plug (UPP), mesh modeling of UPP has been performed for the E-M analysis. Application of HIP (Hot Isostatic Press) method for manufacturing of UPP has been proposed.

Oral presentation

Progress in ITER diagnostics development in Japan

Kawano, Yasunori; Iwamae, Atsushi; Ogawa, Hiroaki; Sugie, Tatsuo; Hatae, Takaki; Yatsuka, Eiichi; Kondoh, Takashi; Ishikawa, Masao; Sato, Kazuyoshi; Hayashi, Toshimitsu; et al.

no journal, , 

no abstracts in English

Oral presentation

Progress of design of the ITER poloidal polarimeter

Kawano, Yasunori; Ishikawa, Masao; Kusama, Yoshinori; Hayashi, Toshimitsu; Ono, Takehiro; Ebisawa, Katsuyuki*; Wakabayashi, Kuniaki*; Kiyohara, Motosuke*

no journal, , 

no abstracts in English

Oral presentation

Progress in ITER diagnostics development in Japan

Kawano, Yasunori; Kondoh, Takashi; Ishikawa, Masao; Ogawa, Hiroaki; Iwamae, Atsushi; Sugie, Tatsuo; Sato, Kazuyoshi; Hatae, Takaki; Yatsuka, Eiichi; Hayashi, Toshimitsu; et al.

no journal, , 

no abstracts in English

Oral presentation

Status and plan of ITER diagnostics development

Kusama, Yoshinori; Kawano, Yasunori; Sugie, Tatsuo; Kondoh, Takashi; Ogawa, Hiroaki; Hatae, Takaki; Sato, Kazuyoshi; Suzuki, Satoshi; Hayashi, Toshimitsu; Ono, Takehiro; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of high power laser for the edge Thomson scattering system in ITER

Hatae, Takaki; Yatsuka, Eiichi; Hayashi, Toshimitsu; Kajita, Shin*; Yoshida, Hidetsugu*; Fujita, Hisanori*; Nakatsuka, Masahiro*; Shinobu, Katsuya*; Yahagi, Kenichi*; Takematsu, Hiroyuki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Status of design of the ITER poloidal polarimeter

Kawano, Yasunori; Ishikawa, Masao; Sato, Kazuyoshi; Kusama, Yoshinori; Hayashi, Toshimitsu; Ono, Takehiro; Ebisawa, Katsuyuki*; Wakabayashi, Kuniaki*; Hiramatsu, Miho*; Kiyohara, Michio*; et al.

no journal, , 

no abstracts in English

Oral presentation

Progress in the design of the ITER poloidal polarimeter

Kawano, Yasunori; Ishikawa, Masao; Sato, Kazuyoshi; Imazawa, Ryota; Kusama, Yoshinori; Hayashi, Toshimitsu; Ono, Takehiro; Ebisawa, Katsuyuki*; Wakabayashi, Kuniaki*; Hiramatsu, Miho*; et al.

no journal, , 

Oral presentation

Present staatus of edge Thomson scattering system in ITER

Hatae, Takaki; Yatsuka, Eiichi; Hayashi, Toshimitsu; Ono, Takehiro; Kusama, Yoshinori

no journal, , 

Oral presentation

Progress in development of high power laser for the edge Thomson scattering system in ITER

Hatae, Takaki; Yatsuka, Eiichi; Hayashi, Toshimitsu; Yoshida, Hidetsugu*; Takematsu, Hiroyuki*; Ono, Takehiro; Kusama, Yoshinori; Fujita, Hisanori*; Nakatsuka, Masahiro*

no journal, , 

no abstracts in English

Oral presentation

Development of a prototype YAG laser amplifier for the edge Thomson scattering system in ITER

Hatae, Takaki; Hayashi, Toshimitsu; Yatsuka, Eiichi; Yoshida, Hidetsugu*; Fujita, Hisanori*; Nakatsuka, Masahiro*; Ono, Takehiro; Kusama, Yoshinori

no journal, , 

Oral presentation

Magnetic property variation of the austenitic stainless steels irradiated in JOYO

Hayashi, Takehiro; Takaya, Shigeru; Nagae, Yuji; Konno, Shotaro; Yamagata, Ichiro

no journal, , 

Structural materials in nuclear plants are affected to aging degradation and irradiation damage. Nondestructive measurement of materials damage is a preferred method for the diagnosis of nuclear plants. The previous studies are focused on magnetic property, which is able to measure by nondestructive and sensitive for microstructure and variation of local chemical compositions. However, whole sample is needed to magnetize by large magnets in the previous method, and the sample is easily influenced by magnetic flux at the edge of sample. This issue makes magnetic method difficult to apply to nuclear plants. The pointing magnetization technique was developed for a local magnetization of samples with a small magnet. It is the first time to apply this method on austenitic stainless steels for fast reactor structural material. The measurement results show that austenitic steels have increased magnetic flux density as dose increases. And magnetic flux density is dependent on irradiation temperature. These results indicate pointing magnetize technique suggested the possibility of the irradiation damage evaluation of austenitic stainless steel.

35 (Records 1-20 displayed on this page)