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Kaji, Yoshiyuki; Nemoto, Yoshiyuki; Nagatake, Taku; Yoshida, Hiroyuki; Tojo, Masayuki*; Goto, Daisuke*; Nishimura, Satoshi*; Suzuki, Hiroaki*; Yamato, Masaaki*; Watanabe, Satoshi*
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05
In this research program, cladding oxidation model in SFP accident condition, and numerical simulation method to evaluate capability of spray cooling system which was deployed for spent fuel cooling during SFP accident, have been developed. These were introduced into the severe accident codes such as MAAP and SAMPSON, and SFP accident analyses were conducted. Analyses using Computational Fluid Dynamics (CFD) code were conducted as well for the comparison with SA code analyses and investigation of detail in the SFP accident. In addition, three-dimensional criticality analysis method was developed as well, and safer loading pattern of spent fuels in pool was investigated.
Someya, Takayuki*; Chitose, Hiromasa*; Watanabe, Satoshi*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki
Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 9 Pages, 2019/05
In this study, CFD analysis has been conducted for the assessment of spent fuel integrity in large LOCA event and the maximum temperature of spent fuel assemblies has been evaluated. Then, it has been compared with the result of the simple assessment method. As a case study, additional CFD analysis has been conducted, where water level in SFP decreases to the Bottom of Active Fuel (BAF) due to boil-off. Since this scenario might be more severe than large LOCA scenario, the number of spent fuel assemblies, their decay heat and loading pattern to maintain spent fuel integrity are investigated.
Wakai, Eiichi; Kanemura, Takuji; Kondo, Hiroo; Hirakawa, Yasushi; Ito, Yuzuru*; Higashi, Takuma*; Suzuki, Akihiro*; Fukada, Satoshi*; Yagi, Juro*; Tsuji, Yoshiyuki*; et al.
Nuclear Materials and Energy (Internet), 9, p.278 - 285, 2016/12
Times Cited Count：11 Percentile：64.98(Nuclear Science & Technology)The EVEDA (Engineering Validation and Engineering Design Activity) lithium test loop with the world's highest flow rate was constructed and has been operated mainly at 250
C. It succeeded in generating a 100 mm wide and 25 mm thick free-surface lithium flow along a concave back plate steadily at a high-speed of 15 m/s at 250C for 1,300 h under the Broader Approach Activities. A new wave height measuring method (laser-probe method) was developed for measurements of the 3D geometry of the liquid Li target surface. Using the device, the stability of the Li flow (the thickness variation of 
1 mm or less) required for the actual liquid Li target of the IFMIF was satisfied and the feasibility of the long-term stable liquid Li flow was verified. The results of the other engineering validation tests such as lithium purification tests and the engineering design of lithium facility have also been evaluated and summarized.
Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Watanabe, Kazuyoshi; Ida, Mizuho*; Ito, Yuzuru; Niitsuma, Shigeto; Edao, Yuki; et al.
Fusion Science and Technology, 66(1), p.46 - 56, 2014/07
Times Cited Count：4 Percentile：27.37(Nuclear Science & Technology)Wakai, Eiichi; Kondo, Hiroo; Sugimoto, Masayoshi; Fukada, Satoshi*; Yagi, Juro*; Ida, Mizuho; Kanemura, Takuji; Furukawa, Tomohiro; Hirakawa, Yasushi; Watanabe, Kazuyoshi; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 88(12), p.691 - 705, 2012/12
no abstracts in English
Nakamura, Kazuyuki; Furukawa, Tomohiro; Hirakawa, Yasushi; Kanemura, Takuji; Kondo, Hiroo; Ida, Mizuho; Niitsuma, Shigeto; Otaka, Masahiko; Watanabe, Kazuyoshi; Horiike, Hiroshi*; et al.
Fusion Engineering and Design, 86(9-11), p.2491 - 2494, 2011/10
Times Cited Count：11 Percentile：60.58(Nuclear Science & Technology)In IFMIF/EVEDA, tasks for lithium target system are shared to 5 validation tasks (LF1-5) and a design task (LF6). The purpose of LF1 task is to construct and operate the EVEDA lithium test loop, and JAEA has a main responsibility to the performance of the Li test loop. LF2 is a task for the diagnostics of the Li test loop and IFMIF design. Basic research for the diagnostics equipment has been completed, and the construction for the Li test loop will be finished before March in 2011. LF4 is a task for the purification systems with nitrogen and hydrogen. Basic research for the purification equipment has been completed, and the construction of the nitrogen system for the Li test loop will be finished before March in 2011. LF5 is a task for the remote handling system with the target assembly. JAEA has an idea to use the laser beam for cutting and welding of the lip part of the flanges. LF6 is a task for the design of the IFMIF based on the validation experiments of LF1-5.
Ida, Mizuho; Fukada, Satoshi*; Furukawa, Tomohiro; Hirakawa, Yasushi; Horiike, Hiroshi*; Kanemura, Takuji*; Kondo, Hiroo; Miyashita, Makoto; Nakamura, Hiroo; Sugiura, Hirokazu*; et al.
Journal of Nuclear Materials, 417(1-3), p.1294 - 1298, 2011/10
Times Cited Count：4 Percentile：30.56(Materials Science, Multidisciplinary)Engineering Validation and Engineering Design Activities (EVEDA) of the International Fusion Materials Irradiation Facility (IFMIF) was started. As a Japanese activity for the target system, EVEDA Lithium Test Loop simulating hydraulic and impurity conditions of IFMIF is under design and preparation for fabrication. Feasibility of thermo-mechanical structure of the target assembly and the replaceable back-plate made of F82H (a RAFM) and 316L (a stainless steel) is a key issue. Toward final validation on the EVEDA loop, diagnostics applicable to a high-speed free-surface Li flow and hot traps to control nitrogen and hydrogen in Li are under tests. For remote handling of target assemblies and the replaceable back-plates activated up to 50 dpa/y, lip weld on 316L-316L by laser and dissimilar weld on F82H-316L are under investigation. As engineering design of the IFMIF target system, water experiments and hydraulic/thermo-mechanical analyses of the back-plate are going.
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Bunseki Kagaku, 16(13), p.96R - 122R, 1967/00
no abstracts in English
Nakamura, Kazuyuki; Ida, Mizuho; Kanemura, Takuji; Kondo, Hiroo; Niitsuma, Shigeto; Hirakawa, Yasushi; Furukawa, Tomohiro; Watanabe, Kazuyoshi; Horiike, Hiroshi*; Terai, Takayuki*; et al.
no journal, ,
I will present the outline and the status of the Japanese tasks for the Li Target system, which is ongoing now under the International Fusion Material Irradiation Facility (IFMIF)/Engineering Validation and Engineering Design Activities (EVEDA). The latest progresses are a completion of the EVEDA Li Loop, a fablication of the remote handling equipment and a repair from the damages caused by the earthquake.
Shiina, Akira; Yamashita, Takuya; Watanabe, Toshio; Imai, Yoshiyuki*; Ono, Koichi*
no journal, ,
no abstracts in English
Nakamura, Kazuyuki; Ida, Mizuho; Kanemura, Takuji; Kondo, Hiroo; Niitsuma, Shigeto; Hirakawa, Yasushi; Furukawa, Tomohiro; Watanabe, Kazuyoshi; Horiike, Hiroshi; Terai, Takayuki*; et al.
no journal, ,
Three and half years has been passed from the start of IFMIF/EVEDA. In IFMIF/EVEDA, tasks for Lithium Target System consists of 5 validation tasks (LF1-5) and a design task (ED3), and are shared by Japan and Europe. Japan is covering the construction and operation of EVEDA Li Test Loop (LF1), diagnostics (LF2), purification system (LF4), remote handling system (LF5) and engineering design (ED3) with the contribution from universities. The present status of these tasks will be reported in the conference.
Wakai, Eiichi; Watanabe, Kazuyoshi; Ida, Mizuho*; Kondo, Hiroo; Kanemura, Takuji; Niitsuma, Shigeto*; Fujishiro, Koji; Ito, Yuzuru; Nakaniwa, Koichi; Sugimoto, Masayoshi; et al.
no journal, ,
Chitose, Hiromasa*; Watanabe, Satoshi*; Sadamatsu, Hideaki*; Iwata, Yutaka*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki
no journal, ,
We researched the recent enhancements of regulations and solutions related Spent Fuel Pool safety and reported the analytical results about problems and evaluation procedures related effectiveness evaluation of safety measures.
Nakamura, Kazuyuki; Ida, Mizuho; Kondo, Hiroo; Watanabe, Kazuyoshi; Furukawa, Tomohiro; Hirakawa, Yasushi; Horiike, Hiroshi*; Fukada, Satoshi*; Terai, Takayuki*; Tsuji, Yoshiyuki*; et al.
no journal, ,
IFMIF/EVEDA started at July in 2007. Li Target System consists of five validation tasks (LF1-5) and one design task (LF6). Present status of Li Test Loop Construction and Operation task (LF1) is to complete the fabrication and installation of the almost key components except Target Assembly and Two types of traps for nitrogen and hydrogen, and to continue the connection with the components by the pipes. In the Diagnostics task (LF2), the characterization of the contact probe level meter is on going in Osaka University. In the Purification System task (LF4), the characterization of the Fe-Ti gettering material in Tokyo University and of Y gettering material in Kyushu University is on going. In the Remote Handling task (LF5), the design of the experimental facility has been finished. In the Engineering Design task (LF6), the engineering design for the IFMIF will be completed based on the validation tasks (LF1-5).
