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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 
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.
113 of the 113th elementMorita, Kosuke*; Morimoto, Koji*; Kaji, Daiya*; Haba, Hiromitsu*; Ozeki, Kazutaka*; Kudo, Yuki*; Sumita, Takayuki*; Wakabayashi, Yasuo*; Yoneda, Akira*; Tanaka, Kengo*; et al.
Journal of the Physical Society of Japan, 81(10), p.103201_1 - 103201_4, 2012/10
Times Cited Count：157 Percentile：97.26(Physics, Multidisciplinary)An isotope of the 113th element, 113, was produced in a nuclear reaction with a 
Zn beam on a 
Bi target. We observed six consecutive 
decays following the implantation of a heavy particle in nearly the same position in the semiconductor detector, in extremely low background condition. The fifth and sixth decays are fully consistent with the sequential decays of 
Db and 
Lr both in decay energies and decay times. This indicates that the present decay chain consisted of 113, 
Rg (Z = 111), 
Mt (Z = 109), 
Bh (Z = 107), Db (Z = 105), and Lr (Z = 103) with firm connections. This result, together with previously reported results from 2004 and 2007, conclusively leads the unambiguous production and identification of the isotope 113, of the 113th element.
Fujita, Mitsutane*; Xu, Y.*; Kaji, Yoshiyuki; Tsukada, Takashi; Mashiko, Shinichi*; Onose, Shoji*
RIST News, (38), p.3 - 14, 2004/11
The distributed materials database system named "Data-Free-Way(DFW)" has been developed with the collaboration of three organizations: the National Institute for Materials Science, the Japan Atomic Energy Research Institute, and the Japan Nuclear Cycle Development Institute over the Internet since 1990. At present, the development of a distributed knowledge based system, in which knowledge extracted from DFW is expressed, is planned with the collaboration of three organizations as we add data into DFW and make DFW open for the public use. Network technique and presentation and acquisition technique of the information developed rapidly and these techniques brought about a revolution in the society and our daily life changed. This paper describe the present status of DFW and future direction of the material databases with the transition of information technology.
Kaji, Yoshiyuki; Tsuji, Hirokazu; Fujita, Mitsutane*; Xu, Y.*; Yoshida, Kenji*; Mashiko, Shinichi*; Shimura, Kazuki*; Miyakawa, Shunichi*; Ashino, Toshihiro*
Data Science Journal (Internet), 3, p.88 - 94, 2004/07
The distributed material database system named "Data-Free-Way" has been developed by four organizations (the National Institute for Materials Science, the Japan Atomic Energy Research Institute, the Japan Nuclear Cycle Development Institute, and the Japan Science and Technology Corporation) under a cooperative agreement. In order to create additional values of the system, knowledge base system, in which knowledge extracted from the material database is expressed, is planned to be developed for more effective utilization of Data-Free-Way. XML (eXtensible Markup Language) has been adopted as the description method of the retrieved results and the meaning of them. One knowledge note described with XML is stored as one knowledge which composes the knowledge base. This paper describes the current status of Data-Free-Way, the description method of knowledge extracted from the material database with XML and the distributed material knowledge base system.
Kaji, Yoshiyuki; Tsukada, Takashi; Fujita, Mitsutane*; Kinugawa, Junichi*; Yoshida, Kenji*; Mashiko, Shinichi*; Onose, Shoji*; Iwata, Shuichi*
2003-Nen Johogaku Shimpojiumu Koen Rombunshu, p.89 - 92, 2003/01
The distributed material database system named 'Data-Free-Way' has been developed by four organizations (the National Institute for Materials Science, the Japan Atomic Energy Research Institute, the Japan Nuclear Cycle Development Institute, and the Japan Science and Technology Corporation) under a cooperative agreement. In order to create additional values of the system, knowledge base system, in which knowledge extracted from the material database is expressed, is planned to be developed for more effective utilization of Data-Free-Way. XML (eXtensible Markup Language) has been adopted as the description method of the retrieved results and the meaning of them. This paper will describe the description method of knowledge extracted from the material database with XML and the distributed material knowledge base system.
Kaji, Yoshiyuki; Yoshida, Kenji*; Mashiko, Shinichi*; Fujita, Mitsutane*; Shimura, Kazuki*; Kinugawa, Junichi*; Tsuji, Hirokazu; Miyakawa, Shunichi*; Iwata, Shuichi*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.412 - 418, 2002/12
The distributed material database system named 'Data-Free-Way' has been developed by four organizations (the National Institute for Materials Science, the Japan Atomic Energy Research Institute, the Japan Nuclear Cycle Development Institute, and the Japan Science and Technology Corporation) under a cooperative agreement. In order to create additional values of the system, knowledge base system, in which knowledge extracted from the material database is expressed, is planned to be developed for more effective utilization of Data-Free-Way. XML (eXtensible Markup Language) has been adopted as the description method of the retrieved results and the meaning of them. One knowledge note described with XML is stored as one knowledge which composes the knowledge base. This paper describes the current status of Data-Free-Way, the description method of knowledge extracted from the material database with XML and the distributed material knowledge base system.
Tsuji, Hirokazu; Kaji, Yoshiyuki; Fujita, Mitsutane*; Kinugawa, Junichi*; Yoshida, Kenji*; Mashiko, Shinichi*; Shimura, Kazuki*; Miyakawa, Shunichi*; Iwata, Shuichi*
Proceedings of 10th German-Japanese Workshop on Chemical Information, p.131 - 133, 2002/00
The distributed material database system named "Data-Free-Way" has been developed by four organizations (the National Institute for Materials Science, the Japan Atomic Energy Research Institute, the Japan Nuclear Cycle Development Institute and Japan Science and Technology Corporation) under a cooperative agreement. It is a system which can display the data which the user demands without considering the organization which stores data as a table and a graph. The knowledge of the forte of each organization based on the retrieval result from the fact database is made aiming at more highly developed use of this system. The development of the system by which the user can refer to the knowledge is advanced. Though the retrieval result from the fact database was displayed as a table and a graph, that is, the finding note where they were described and expressed with XML as knowledge.
Kaji, Yoshiyuki; Yoshida, Kenji*; Mashiko, Shinichi*; Fujita, Mitsutane*; Shimura, Kazuki*; Kinugawa, Junichi*; Tsuji, Hirokazu; Miyakawa, Shunichi*; Iwata, Shuichi*
Dai-38-Kai Joho Kagaku Gijutsu Kenkyu Shukai Happyo Yokoushu, p.43 - 47, 2001/00
A distributed database system named Data-Free-Way for advanced nuclear materials has been developed by the National Institute for Materials Science (NIMS), the Japan Atomic Energy Research Institute (JAERI), the Japan Nuclear Cycle Development Institute (JNC), and the Japan Science and Technology Corporation (JST) under a cooperative agreement. In this system, end-users are able to obtain necessary data such as tables or graphs, even if they do not know the sites in which the data are stored. A distributed knowledge database in which each organization makes the knowledge based on the retrieval results from fact database and end-users can get the knowledge, has been developed to make more useful utilization of this system. Though the retrieval results from the fact database were shown in the tables or graphs, the new system constitutes the information notes described the retrieval ones for the knowledge by XML. This paper describes the present status of the Data-Free-Way and the description method of XML for the retrieval results.
Kinugawa, Junichi*; Fujita, Mitsutane*; Noda, Tetsuji*; Tsuji, Hirokazu; Kaji, Yoshiyuki; Sakino, Takao*; Tachi, Yoshiaki*; Kaneda, Kenichiro*; Mashiko, Shinichi*; Shimura, Kazuki*; et al.
Proceedings of 9th German-Japanese Workshop on Chemical Information, p.134 - 135, 2000/00
no abstracts in English
Hayashi, Takehiro; Sasaki, Shinji; Mashiko, Shinichi; Yamagata, Ichiro; Ogawa, Ryuichiro; Inoue, Masaki; Yamashita, Shinichiro; Maeda, Koji
no journal, ,
no abstracts in English
Sekio, Yoshihiro; Yamagata, Ichiro; Yamashita, Shinichiro; Sasaki, Shinji; Ogawa, Ryuichiro; Mashiko, Shinichi; Hayashi, Takehiro; Inoue, Toshihiko; Inoue, Masaki; Maeda, Koji
no journal, ,
Corrosion and mechanical property tests utilizing spent fuel cladding made of zircaloy-2 were performed as a tentative test of the project for the purpose of simulating an environment at the very early stage after the accident in the SFP of unit 4 in the Fukushima Dai-ichi Nuclear Power Plant. The result of metallurgical investigation after corrosion test showed that no obvious changes in oxide film formed on the outer surface of cladding such as stripping occurred. In addition to that, the ring-tensile test results of samples after corrosion test was obtained and compared with that of samples before corrosion test, indicating that no significant degradation in mechanical property was confirmed. These results would have indicated that integrity of FAs was kept to be high as same as what it was before conducting corrosion test.
Yamagata, Ichiro; Hayashi, Takehiro; Sasaki, Shinji; Mashiko, Shinichi; Inoue, Masaki; Yamashita, Shinichiro; Maeda, Koji
no journal, ,
In the accident on Fukushima Dai-ichi Nuclear Power Plant, the spent fuel pool was cooled by sea water. To investigate soundness evaluation of fuel assemblies in the pool, immersion tests were conducted for irradiated zircaloy-2 cladding tubes and the results were reported in 2012 Fall Meeting of Atomic Energy Society of Japan. In this report, the same tests were performed in the more corrosive conditions of artificial sea water concentration and extended immersion time, and the influence of artificial sea water concentration on corrosion behavior and tensile properties of zircaloy-2 cladding tubes were evaluated.
Hayashi, Takehiro; Sasaki, Shinji; Mashiko, Shinichi*; Yamagata, Ichiro; Ogawa, Ryuichiro; Inoue, Masaki; Yamashita, Shinichiro
no journal, ,
In the Great East Japan Earthquake, the Fukushima Dai-ichi Nuclear Power Plants (1F) were in station blackout and dropped their cooling power. To cool the plants, seawater was poured into 1F buildings included SFP. In this study, the immersion tests were carried out with artificial seawater to evaluate the effect on the strength properties of Zircaloy-2 cladding tubes in seawater. The results indicated the growth of corrosion was not observed in microstructures on the surface of Zircaloy-2 tubes, and there were no significant changes in the tensile properties.
Hayashi, Takehiro; Yamagata, Ichiro; Mashiko, Shinichi*; Sasaki, Shinji; Yamashita, Shinichiro; Inoue, Masaki; Maeda, Koji
no journal, ,
In the accident on Fukushima Dai-ichi Nuclear Power Plant, the spent fuel pool was cooled by sea water. To investigate soundness evaluation of fuel assemblies in the pool, immersion tests were conducted for irradiated zircaloy-2 cladding tubes and the results were reported in 2013 Fall Meeting of Atomic Energy Society of Japan. In this report, the same tests were performed in the more corrosive conditions of artificial sea water concentration and extended immersion time, and the influence of artificial sea water concentration on corrosion behavior and tensile properties of Zircaloy-2 cladding tubes were evaluated.
Sekio, Yoshihiro; Hayashi, Takehiro; Yamagata, Ichiro; Sasaki, Shinji; Mashiko, Shinichi*; Inoue, Masaki; Yamashita, Shinichiro; Maeda, Koji
no journal, ,
In the Fukushima Dai-ichi Nuclear Power Plant accident, seawater was temporarily injected into the spent fuel pools since water cooling and feeding functions were lost. For fuel assemblies which experienced seawater immersion, surface corrosion due to seawater constituents and the resultant degradation of mechanical property are of concern. Therefore, in order to assess the integrity of cladding tubes, the effects of seawater immersion on corrosion behavior and mechanical properties for especially irradiated Zircaloy-2 cladding tube were investigated in the present study. As a result, no obvious surface corrosion and no significant degradation in the tensile strength property were observed after both artificial and natural seawater immersion tests. This suggests that the effects of seawater immersions on corrosion behavior and mechanical property (especially tensile property) for irradiated Zircaloy-2 cladding tube are probably negligible.
