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Nakayama, Takuya; Yagi, Naoto; Sato, Kazuhiko; Hinoda, Shingo; Nakagiri, Toshio; Morimoto, Yasuyuki; Umezawa, Katsuhiro; Sugitsue, Noritake
JAEA-Review 2018-005, 163 Pages, 2018/03
JAEA-Review-2018-005.pdf:72.95MB
The Ningyo-toge Environmental Engineering Center of JAEA has been working together with local communities for more than 60 years. Through our R&D projects on from uranium exploration to uranium enrichment as a part of the nuclear fuel cycle (i.e., front-end), we have accumulated experiences in the fields of management of uranium related technology. Taking advantage of such our potential, we will start new R&D program on "Research on Uranium and the Environment". In December 2016 we announced our new concept of the "Uranium and Environmental Research Platform" as a framework aimed at contributing to regional and international society through R&D programs (environmental research and uranium waste engineering research) that are needed to steadily carry out decommissioning of uranium handling facilities.
Abe, Tomohisa; Shimazaki, Takejiro; Nakayama, Takuya; Osone, Osamu; Osugi, Takeshi; Nakazawa, Osamu; Yuri, Yosuke*; Yamada, Naoto*; Sato, Takahiro*
QST-M-2; QST Takasaki Annual Report 2015, P. 83, 2017/03
no abstracts in English
Usui, Toshihide; Mikami, Satoshi; Hashimoto, Makoto; Nakayama, Naoto; Suzuki, Chihiro*; Tani, Kotaro*; Yamasaki, Keizo*; Misawa, Tsuyoshi*
KURRI Progress Report 2010, P. 209, 2011/10
no abstracts in English
Kamide, Hideki; Aizawa, Kosuke; Oshima, Jun*; Nakayama, Okatsu*; Kasahara, Naoto
Journal of Nuclear Science and Technology, 47(9), p.810 - 819, 2010/09
Times Cited Count：3 Percentile：23.38(Nuclear Science & Technology)Development of advanced loop type sodium cooled fast reactor is under going. An upper internal structure (UIS) has a radial slit to reduce the reactor vessel diameter. This UIS slit allows a high velocity from the core fuel subassemblies and influences the gas entrainment in the reactor vessel and also the delayed neutron precursor sampling for a failed fuel detection and location system. Then flow visualization and velocity measurements were carried out in an 1/10 scale water test model. The velocity measurement using particle image velocimetry showed that velocity in the slit region was accelerated at the heights of the UIS horizontal plates and kept higher value at the middle height of the upper plenum. Numerical simulation using a commercial CFD code was also carried out for this complex geometry of UIS to know adequate simulation method. The comparisons of velocity profiles in the UIS between the experiment and analysis showed good agreements.
Kamide, Hideki; Aizawa, Kosuke; Oshima, Jun*; Nakayama, Okatsu*; Kasahara, Naoto
Proceedings of 6th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-6) (USB Flash Drive), 8 Pages, 2008/11
Development of advanced loop type sodium cooled fast reactor is under going. An upper internal structure (UIS) has a radial slit to reduce the reactor vessel diameter. This UIS slit allows a high velocity from the core fuel subassemblies and influences the gas entrainment in the reactor vessel and also the delayed neutron precursor sampling for a failed fuel detection and location system. Then flow visualization and velocity measurements were carried out in an 1/10 scale water test model. The velocity measurement using particle image velocimetry showed that velocity in the slit region was accelerated at the heights of the UIS horizontal plates and kept higher value at the middle height of the upper plenum. Numerical simulation using a commercial CFD code was also carried out for this complex geometry of UIS to know adequate simulation method. The comparisons of velocity profiles in the UIS between the experiment and analysis showed good agreements.
Isobe, Nobuhiro*; Sukekawa, Masayuki*; Nakayama, Yasunari*; Date, Shingo*; Otani, Tomomi*; Takahashi, Yukio*; Kasahara, Naoto; Shibamoto, Hiroshi*; Nagashima, Hideaki*; Inoue, Kazuhiko*
Nuclear Engineering and Design, 238(2), p.347 - 352, 2008/02
Times Cited Count：22 Percentile：77.77(Nuclear Science & Technology)The effect of ratcheting on fatigue strength was investigated in order to rationalize the strain limit as a design criterion of commercialized fast reactor systems. Ratcheting fatigue tests were conducted at 550
C. Duration of the ratchet straining was set for a certain number of strain cycles taking the loading condition of fast reactors into account, and the number of cycles for strain accumulation was defined as the ratchet-expired cycle. Fatigue lives decrease as the accumulated strain by ratcheting increases. Fatigue life reduction was negligible when the maximum mean stress was less than 25 MPa, corresponding to an accumulated strain of 2.2 percent. Accumulated strain is limited to 2 percent in the present design guidelines and this strain limit is considered effective to avoid reducing fatigue life by ratcheting. Micro-crack growth behaviors were also investigated in these tests in order to discuss the life reduction mechanisms in ratcheting conditions.
Uehara, Tomoya*; Koike, Miho*; Nakata, Hideo*; Miyamoto, Shigehiko*; Motoishi, Shoji; Hashimoto, Kazuyuki; Oku, Naoto*; Nakayama, Morio*; Arano, Yasushi*
Nuclear Medicine and Biology, 30(3), p.327 - 334, 2003/04
Times Cited Count：20 Percentile：49.54(Radiology, Nuclear Medicine & Medical Imaging)no abstracts in English
Abe, Tomohisa; Shimazaki, Takejiro; Nakayama, Takuya; Osone, Osamu; Osugi, Takeshi; Nakazawa, Osamu; Yuri, Yosuke*; Yamada, Naoto*; Sato, Takahiro*
no journal, ,
no abstracts in English
Wada, Rina; Nakayama, Naoto; Nohara, Naofumi; Saito, Kei
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no abstracts in English
Usui, Toshihide; Mikami, Satoshi; Nakayama, Naoto; Hashimoto, Makoto; Suzuki, Chihiro*; Yamasaki, Keizo*; Misawa, Tsuyoshi*
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no abstracts in English
Nakayama, Naoto; Iwasa, Atsutoshi; Hamazaki, Masaaki; Sumiya, Yoshinobu*; Ogiya, Takashi; Irokawa, Hiroyuki; Kano, Yutaka; Takashima, Hideki; Hitomi, Junichi
no journal, ,
no abstracts in English
Nakayama, Naoto; Yatsuda, Kazumi; Hamazaki, Masaaki; Usui, Toshihide; Nakada, Akira
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no abstracts in English
Abe, Tomohisa; Shimazaki, Takejiro; Nakayama, Takuya; Osone, Osamu; Osugi, Takeshi; Nakazawa, Osamu; Yuri, Yosuke*; Yamada, Naoto*; Sato, Takahiro*
no journal, ,
no abstracts in English
Shibamoto, Hiroshi; Inoue, Kazuhiko*; Takahashi, Yukio*; Nakamura, Kyotada*; Kasahara, Naoto; Nakayama, Yasunari*
no journal, ,
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Kuroe, Ayame; Takada, Chie; Takahata, Eiji; Watanabe, Yuki; Hosomi, Kenji; Nakayama, Naoto; Morifuji, Masayuki; Miyauchi, Toru
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no abstracts in English
Usui, Toshihide; Iwai, Ryo; Gomibuchi, Masaru; Nakayama, Naoto; Iwasa, Atsutoshi; Takashima, Hideki; Hitomi, Junichi
no journal, ,
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Iwasa, Atsutoshi; Nakayama, Naoto; Maeda, Eita; Usui, Toshihide; Kano, Yutaka; Takashima, Hideki; Irokawa, Hiroyuki
no journal, ,
no abstracts in English
Nakayama, Takuya; Osugi, Takeshi; Shimazaki, Takejiro; Abe, Tomohisa; Yagi, Naoto; Nakazawa, Osamu; Sato, Haruo*; Suzuki, Kazuhiko*
no journal, ,
The amount of hydrogen generated by the radiation of adjacent cement-solidified wastes, and its effect was evaluated by PHITS code, when dispose them. These results suggested that the amount of hydrogen generation was inhibited by increase the separation distance between the cement-solidified waste, and the waste of high radioactive concentration does not place continuously.
Iwasa, Atsutoshi; Nakayama, Naoto; Mikami, Satoshi; Eguchi, Kazutoshi; Takashima, Hideki; Hitomi, Junichi; Gomibuchi, Masaru*
no journal, ,
no abstracts in English
Usui, Toshihide; Nakayama, Naoto; Iwasa, Atsutoshi; Miura, Yoshiyuki; Ishida, Keiichi; Irokawa, Hiroyuki; Hamazaki, Masaaki; Okawa, Yasuhisa; Iwai, Ryo
no journal, ,
no abstracts in English
-to-
ratio and the result of nuclide analysisNakayama, Naoto; Usui, Toshihide; Gomibuchi, Masaru; Takashima, Hideki; Hitomi, Junichi
no journal, ,
no abstracts in English
