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Journal Articles

Validation of the applicability of the best-fit fatigue curves for 550$$^{circ}$$C in Mod.9Cr-1Mo steel to 1$$times$$10$$^{11}$$ cycles

Toyota, Kodai; Imagawa, Yuya; Onizawa, Takashi; Kato, Shoichi; Furuya, Yoshiyuki*

Nihon Kikai Gakkai Rombunshu (Internet), 89(928), p.23-00206_1 - 23-00206_15, 2023/12

In order to design fast reactors, it is necessary to consider high cycle fatigue of structural materials up to 1$$times$$10$$^{9}$$ cycles; to evaluate high cycle fatigue at 1$$times$$10$$^{9}$$ cycles, it is necessary to develop a best-fit fatigue curve applicable up to 1$$times$$10$$^{11}$$ cycles. In this study, high cycle fatigue tests were conducted under strain-controlled conditions and ultrasonic fatigue tests were also conducted to develop a high cycle fatigue evaluation method for Mod.9Cr-1Mo steel, which is a candidate material for fast reactor structural materials. Based on the test results, the best-fit fatigue curves were extended and the applicability of the JSME best-fit fatigue curves up to 1$$times$$10$$^{11}$$ cycles was verified.

Journal Articles

Engineering validation and engineering design of lithium target facility in IFMIF/EVEDA project

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:30.8(Nuclear Science & Technology)

Journal Articles

Development of lithium target system in engineering validation and engineering design activity of the International Fusion Materials Irradiation Facility (IFMIF/EVEDA)

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

AA2012-1008.pdf:2.42MB

no abstracts in English

Journal Articles

Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA

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:10 Percentile:60.68(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.

Journal Articles

Characteristics and sinterability of MOX powder prepared by the microwave heating denitration method

Asakura, Koichi; Kato, Yoshiyuki; Furuya, Hirotaka

Nuclear Technology, 162(3), p.265 - 275, 2008/06

 Times Cited Count:9 Percentile:52.68(Nuclear Science & Technology)

UO$$_{2}$$, PuO$$_{2}$$ and MOX (mixed oxide of U and Pu) powders were prepared by the MH (microwave heating de-nitration), ADU (Ammonia diuranate) and OX (oxalate) methods. The BET specific surface area, avarage particle size by air permiation method, bulk density, tap density, angle of repose, angle of spatula and cohesiveness of these powders were measured. The degree of surface roughness was evaluated from the ratio of BET surface area to the one calculated from average particle size and then flowability was evaluated on the basis of Carr's theory. These results were compared for the different powders and preperation methods as a parameter of calcination temperature. The degree of surface roughness in MH-MOX powder was larger than in ADU-UO$$_{2}$$ powder and smaller in OX-PuO$$_{2}$$ powder. These results could be understood using the concpt of H$"u$ttig and Tamman temperatures commonly cited in ceramics materials. As already reported for the general papers, the flowabilities of MH-MOX and ADU-UO$$_{2}$$ powders also decreased with increase of compressibility, and their absolute values were below 50 points. According to Carr's theory, the brderline between free-flowing and non-free-flowing powders is from 60 to 69 points. It is, therefore, necessary for the mixed powder of MH-MOX powder, ADU-UO$$_{2}$$ powder and dry recycled MOX scrap powder to be granulated to provide a free flowing feed to the pelletizing press in the MOX pellet fabrication process.

Journal Articles

Design and technology development of solid breeder blanket cooled by supercritical water in Japan

Enoeda, Mikio; Kosaku, Yasuo; Hatano, Toshihisa; Kuroda, Toshimasa*; Miki, Nobuharu*; Homma, Takashi; Akiba, Masato; Konishi, Satoshi; Nakamura, Hirofumi; Kawamura, Yoshinori; et al.

Nuclear Fusion, 43(12), p.1837 - 1844, 2003/12

 Times Cited Count:101 Percentile:93.52(Physics, Fluids & Plasmas)

no abstracts in English

Oral presentation

Present status of Japanese tasks on IFMIF/EVEDA Li target system

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).

Oral presentation

Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA

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.

Oral presentation

Small scale engineering experiments on tumbling granulation method using water for MOX pellet production

Kato, Yoshiyuki; Takahashi, Naoki; Morita, Minoru; Yoshimoto, Katsunobu; Furuya, Hirotaka

no journal, , 

In the fabrication process of oxide fuels for LWRs and FBRs, organic powder is usually mixed as a binder to granulate in prior to pellet pressing. This powder is removed during preliminary heating, however the residue and its decomposed material contaminates inside of the furnace and causes frequent cleaning which results in higher operational cost. If water is used instead of the organic powder, the preliminary heating process is skipped and the new process is free from the residue. This is one of the key benefits of the simplified pelletizing method to where we are advancing. Uranium oxide and uranium plutonium mixed oxide were prepared by the microwave heating method. Tests were carried out using a stirring blade which compresses moderately the powder and mixes the powder and water uniformly. In conclusion, the granule 120 to 140 micron in major diameter and 73 to 77 in flow ability was obtained with water addition rate of 13 wt%, despite the narrow range of operating conditions.

Oral presentation

Present status of Japanese tasks for lithium target facility under IFMIF/EVEDA, 1; Outline of activities

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.

Oral presentation

Progress and scheme of IFMIF/EVEDA project; Lithium target facility

Wakai, Eiichi; Watanabe, Kazuyoshi; Ida, Mizuho*; Kondo, Hiroo; Kanemura, Takuji; Niitsuma, Shigeto*; Fujishiro, Koji; Ito, Yuzuru; Nakaniwa, Koichi; Sugimoto, Masayoshi; et al.

no journal, , 

Oral presentation

R&D of lithium target and test facilities for the fusion neutron source

Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Furukawa, Tomohiro; Kikuchi, Takayuki; Ito, Yuzuru*; Hoashi, Eiji*; Yoshihashi, Sachiko*; Horiike, Hiroshi*; et al.

no journal, , 

no abstracts in English

12 (Records 1-12 displayed on this page)
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