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Hama, Katsuhiro; Mikake, Shinichiro; Ishibashi, Masayuki; Sasao, Eiji; Kuwabara, Kazumichi; Ueno, Tetsuro; Onuki, Kenji*; Beppu, Shinji; Onoe, Hironori; Takeuchi, Ryuji; et al.
JAEA-Review 2015-024, 122 Pages, 2015/11
Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is pursuing a geoscientific research and development project namely the Mizunami Underground Research Laboratory (MIU) Project in crystalline rock environment in order to construct scientific and technical basis for geological disposal of High-level Radioactive Waste (HLW). The MIU Project has three overlapping phases: Surface-based Investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III). The MIU Project has been ongoing the Phase III, as the Phase II was concluded for a moment with the completion of the excavation of horizontal tunnels at GL-500m level in February 2014. This report presents the results of the investigations, construction and collaboration studies in fiscal year 2014.
Takaya, Shigeru; Nagae, Yuji; Yoshitake, Tsunemitsu; Nemoto, Yoshiyuki; Nakano, Junichi; Ueno, Fumiyoshi; Aoto, Kazumi; Tsukada, Takashi
E-Journal of Advanced Maintenance (Internet), 1(1), p.44 - 51, 2009/05
As the result of comparing the magnetic flux density and the IASCC susceptibility evaluated by SSRT test on neutron irradiated model alloys, it was shown that there is the relation without depending on dose level and chemical compositions as long as the contribution of neutron irradiation to SCC was seen. Furthermore, measuring the magnetic flux density of unirradiated simulated degraded materials indicates that not only change in chemical compositions but also some defects are needed for the magnetic flux density to increase. These results show the possibility of non-destructive estimation of susceptibility to IASCC by measuring magnetic flux density.
Ueno, Fumiyoshi*; Nagae, Yuji; Nemoto, Yoshiyuki*; Miwa, Yukio*; Takaya, Shigeru; Hoshiya, Taiji; Tsukada, Takashi*; Aoto, Kazumi; Ishii, Toshimitsu*; Omi, Masao*; et al.
JNC TY9400 2005-013, 150 Pages, 2005/09
None
Ueno, Fumiyoshi; Nagae, Yuji*; Nemoto, Yoshiyuki; Miwa, Yukio; Takaya, Shigeru*; Hoshiya, Taiji*; Tsukada, Takashi; Aoto, Kazumi*; Ishii, Toshimitsu; Omi, Masao; et al.
JAERI-Research 2005-023, 132 Pages, 2005/09
JAERI and JNC have started a JAERI-JNC joint research program in fiscal year 2003, which has been aimed for efficient progress and synergistic effect on the research activities in both Institutes. This study has been chosen one of the joint research themes because it has been our common objective in the field of structural materials of FBR and LWR components. The purpose of the study is to clarify damage mechanism of structural materials used under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage. In fiscal year 2004 and 2005, micro-corrosion measurement, electrochemical corrosion test and leakage magnetic flux density measurement apparatuses were developed and equipped in two hot facilities and irradiated and unirradiated crept specimens, irradiated high purity model austenitic stainless alloys were also prepared and applied to this study. These apparatuses and specimens were used for damage evaluation, and these feasibilities for nuclear power plant materials were studied.
Hoshiya, Taiji; Ueno, Fumiyoshi*; Takaya, Shigeru; Nagae, Yuji; Nemoto, Yoshiyuki*; Miwa, Yukio*; Aoto, Kazumi; Tsukada, Takashi*; Abe, Yasuhiro; Nakamura, Yasuo; et al.
JNC TY9400 2004-026, 53 Pages, 2004/10
Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Energy Research Institute (JAERI) have started a JNC-JAERI united research program cooperatively in 2003, which has been aimed for efficient progress and synergistic effect on the research activities of both Institutes in order to lead the facing task of unification between JNC and JAERI. This study has been chosen one of the united research themes, and the purpose of it is to clarify damage mechanism of structural materials under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage. In fiscal year 2003, magnetic flux density distribution (JNC) and micro-corrosion (JAERI) measurement apparatus were newly developed and equipped in Hot Facilities in two Institutes, respectively. These apparatus were designed and produced in consideration of radiation resistance and remote-controlled operation to equip in hot cells. We will start the study on neutron irradiation damage by employing the two apparatus as the next step.
Hoshiya, Taiji*; Ueno, Fumiyoshi; Takaya, Shigeru*; Nagae, Yuji*; Nemoto, Yoshiyuki; Miwa, Yukio; Aoto, Kazumi*; Tsukada, Takashi; Abe, Yasuhiro*; Nakamura, Yasuo*; et al.
JAERI-Research 2004-016, 53 Pages, 2004/10
Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Energy Research Institute (JAERI) have started a JNC-JAERI united research program cooperatively in 2003, which has been aimed for efficient progress and synergistic effect on the research activities of both Institutes in order to lead the facing task of unification between JNC and JAERI. This study has been chosen one of the united research themes, and the purpose of it is to clarify damage mechanism of structural materials under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage. In fiscal year 2003, magnetic flux density distribution (JNC) and micro-corrosion (JAERI) measurement apparatus were newly developed and equipped in Hot Facilities in two Institutes, respectively. These apparatus were designed and produced in consideration of radiation resistance and remote-controlled operation to equip in hot cells. We will start the study on neutron irradiation damage by employing the two apparatus as the next step.
Hoshiya, Taiji*; Takaya, Shigeru*; Ueno, Fumiyoshi; Nemoto, Yoshiyuki; Nagae, Yuji*; Miwa, Yukio; Abe, Yasuhiro*; Omi, Masao; Tsukada, Takashi; Aoto, Kazumi*
Transactions of the Materials Research Society of Japan, 29(4), p.1687 - 1690, 2004/06
JAERI and JNC have begun the cooperative research of evaluation techniques of structural material degradation in FBR and LWR, which based on magnetic and corrosion properties along grain boundaries. Magnetic method has been proposed as the one of the non-destructive detection techniques on the early stage of creep-damage before crack initiation for aged structural materials of FBRs. The effects of applied stress on natural magnetization were investigated on paramagnetic stainless steels having creep-damages. On the other hand, corrosion properties and magneto-optical characteristics of ion-irradiated stainless steels in the vicinity of grain boundaries were estimated by AFM and Kerr effect microscope, respectively. These degradations were induced by changes in characteristics in the vicinity of grain boundaries. It is found that the initial level of progressing process of damage can detect changes in magnetic and corrosion properties along grain boundaries of aged and degraded nuclear plants structural materials.
Hoshiya, Taiji; Takaya, Shigeru; Nagae, Yuji; Abe, Yasuhiro; Aoto, Kazumi; Ueno, Fumiyoshi*
IUMRS-ICAM2003 Abstracts, 29, 0 Pages, 2004/00
Japan Atomic Energy Research Institute and Japan Nuclear Cycle Development Institute have begun The cooperative research of novel evaluation techniques of structural material degradation in Fast Breeder Reactor (FBR) and Light Water Reactor (LWR), which based on magnetic and corrosion properties along grain boundaries Magnetic method has been proposed as the one of the innovative non-destructive detection techniques on the early stage of creep-damage before crack initiation for aged structural materials of FBRs. On the other hand, corrosion properties and magneto-optical characteristics of ion-irradiated stainless steel in the vicinity of grain boundaries were estimated by AFM. These degradations were induced by changes in characteristics in the vicinity of grain boundaries, such as chromium depletion. It is found that the initial level of progressing process of damage can detect changes in magnetic and corrosion properties along grain boundaries of aged and degraded nuclear
; ; Wakai, Takashi; Aoto, Kazumi; Ueno, Fumiyoshi; Nagae, Yuji; Kato, Shoichi; Saito, Junichi
JNC TN9400 2003-034, 26 Pages, 2003/05
The structual material of the future Fast Breeder Reactors(FBRs) must be improved to achive some requirements for improvement of safety and economical competitiveness. To prepare the desired data for the structural material development for the future FBRs, some mechanical and chemical tests, i.e. high temterature tensile tests and sodium corrosion tests, of the high-purity Fe-Cr alloys were conducted under the FBR conditions. As a result, following conclusions are obtained; 1) By eliminating the trace elements, high Cr content iron based alloys can be produced. It was clarified that such alloys have good tensile properties and creep strength enough for practical use at elevated temperature. 2) Through the manufacturing of a full size structure using the high purity Fe-50% Cr alloy, it was confirmed that the alloy has good manufacturability enough for practical use."
Suzuki, Satoru; Fujishima, Atsushi; Ueno, Kenichi; Ichikawa, Yasuaki*; Kawamura, Katsuyuki*; Fujii, Naoki*; Shibata, Masahiro; Sato, Haruo; Kitayama, Kazumi*
Nendo Kagaku, 41(2), p.43 - 57, 2001/12
None
; ; ; Furukawa, Tomohiro; Ueno, Fumiyoshi; Aoto, Kazumi
JNC TY9400 2001-005, 37 Pages, 2001/03
None
; ; ; Furukawa, Tomohiro; Ueno, Fumiyoshi; Aoto, Kazumi
JNC TY9400 2001-006, 28 Pages, 2000/03
no abstracts in English
Aoto, Kazumi; ; Ueno, Fumiyoshi; Kawasaki, Hirotsugu; Wada, Yusaku
Nuclear Engineering and Design, 153(1), p.97 - 110, 1994/12
Times Cited Count:56 Percentile:96.49(Nuclear Science & Technology)None
Kawasaki, Hirotsugu; Ueno, Fumiyoshi; Aoto, Kazumi; Ichimiya, Masakazu; Wada, Yusaku
Zairyo, 41(4), p.1773 - 1778, 1992/00
None
Aoto, Kazumi; ; Ueno, Fumiyoshi; Kawasaki, Hirotsugu; Wada, Yusaku
Dai-6-Kai Nichidoku Genshiryoku Kogaku Semina, ,
None
; Aoto, Kazumi; Wada, Yusaku; Ueno, Fumiyoshi
Transactions of 12th International Conference on Structural Mechanics in Reactor Technology (SMiRT-12), ,
None
Ueno, Fumiyoshi; Aoto, Kazumi; Wada, Yusaku
Transactions of 12th International Conference on Structural Mechanics in Reactor Technology (SMiRT-12), ,
None
Kawasaki, Hirotsugu; Ueno, Fumiyoshi; Aoto, Kazumi; Ichimiya, Masakazu; Wada, Yusaku
Zairyo, ,
None