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Journal Articles

Study on ion-irradiation-induced ferromagnetism in FeRh intermetallic compound by means of magnetic Compton scattering

Kosugi, Shinya*; Matsui, Toshiyuki*; Ishikawa, Norito; Ito, Masayoshi*; Sakurai, Yoshiharu*; Aiko, Kazuma*; Shimizu, Hirotaka*; Tahara, Yuki*; Hori, Fuminobu*; Iwase, Akihiro*

Journal of Applied Physics, 109(7), p.07B737_1 - 07B737_3, 2011/04

 Times Cited Count:7 Percentile:31.34(Physics, Applied)

The magnetic Compton profiles of FeRh intermetallic compound were measured to study the ferromagnetism induced by 200 MeV Xe ion irradiation. The magnetic effect at 50 K increases with increasing the ion-fluence. The analysis of the experimental result revealed that the values of spin moment induced by the irradiation were close to the values of magnetization obtained by a superconducting quantum interference device magnetometer, suggesting that the ion irradiation mainly induces the spin magnetic moment.

Journal Articles

Thermo-structural analysis and design consideration of the replaceable backwall in IFMIF liquid lithium target

Nakamura, Hiroo; Ida, Mizuho; Chida, Teruo; Shiba, Kiyoyuki; Shimizu, Katsusuke*; Sugimoto, Masayoshi

Journal of Nuclear Materials, 367-370(2), p.1543 - 1548, 2007/08

 Times Cited Count:2 Percentile:18.75(Materials Science, Multidisciplinary)

The IFMIF is an accelerator-based intense neutron source for testing candidate materials of fusion reactor. Intense neutrons are emitted inside the Li flow through a backwall. The backwall made of 316L stainless steel or RAFM is attached to the target assembly with a lip seal welded by YAG laser. Since the backwall is operating under a severe neutron irradiation of 50 dpa/year and a maximum nuclear heating rate of 25 W/cm$$^{3}$$, thermo-structural design is one of critical issues in a target design. Thermal stress was calculated by ABAQUS code. As a permissible stress, yield strength at 300$$^{circ}$$C was used. In a case of the 316 stainless steel backwall, a maximum thermal stress was more than the permissible stress(164MPa). On the other hand, in case of the F82H backwall, a maximum thermal stress is was below the permissible stress(455MPa). Therefore, F82H is recommended as a backwall material.

JAEA Reports

Thermo-structural analysis of backwall in IFMIF lithium target

Nakamura, Hiroo; Ida, Mizuho; Shimizu, Katsusuke*; Sugimoto, Masayoshi

JAEA-Technology 2007-008, 28 Pages, 2007/03

JAEA-Technology-2007-008.pdf:4.05MB

This report describes results of thermo-structural analysis of a backwall in IFMIF lithium target performed during FY 2003-2006. The IFMIF is an accelerator-based intense neutron source for testing candidate materials for fusion reactors. Intense neutrons are emitted inside the Li flow through a backwall. The backwall is made of 316L stainless steel or RAFM. Since the backwall is operating under a severe neutron irradiation of 50 dpa/year and a maximum nuclear heating rate of 25 W/cm$$^{3}$$, thermo-structural design is one of critical issues in a target design. Thermal stress was calculated using the ABAQUS code. In a case of the 316L stainless steel backwall, the maximum thermal stress was beyond the permissible stress. On the other hand, in a case of the F82H backwall, a maximum thermal stress was 289 MPa below the permissible stress (455 MPa). Therefore, F82H is recommended as the backwall material.

JAEA Reports

Review of JAERI activities on the IFMIF liquid lithium target in FY2004

Nakamura, Hiroo; Ida, Mizuho*; Matsuhiro, Kenjiro; Fischer, U.*; Hayashi, Takumi; Mori, Seiji*; Nakamura, Hirofumi; Nishitani, Takeo; Shimizu, Katsusuke*; Simakov, S.*; et al.

JAERI-Review 2005-005, 40 Pages, 2005/03

JAERI-Review-2005-005.pdf:3.52MB

The International Fusion Materials Irradiation Facility (IFMIF) is being jointly planned to provide an accelerator-based Deuterium-Lithium (Li) neutron source to produce intense high energy neutrons (2 MW/m$$^{2}$$) up to 200 dpa and a sufficient irradiation volume (500 cm$$^{3}$$) for testing the candidate materials and components up to about a full lifetime of their anticipated use in ITER and DEMO. To realize such a condition, 40 MeV deuteron beam with a current of 250 mA is injected into high speed liquid Li flow with a speed of 20 m/s. In target system, radioactive species such as 7Be, tritium and activated corrosion products are generated. In addition, back wall operates under severe conditions of neutron irradiation damage (about 50 dpa/y). In this paper, the thermal and thermal stress analyses, the accessibility evaluation of the IFMIF Li loop, and the tritium inventory and permeation of the IFMIF Li loop are summarized as JAERI activities on the IFMIF target system performed in FY2004.

Journal Articles

Present status of the liquid lithium target facility in the international fusion materials irradiation facility (IFMIF)

Nakamura, Hiroo; Riccardi, B.*; Loginov, N.*; Ara, Kuniaki*; Burgazzi, L.*; Cevolani, S.*; Dell'Ocro, G.*; Fazio, C.*; Giusti, D.*; Horiike, Hiroshi*; et al.

Journal of Nuclear Materials, 329-333(1), p.202 - 207, 2004/08

 Times Cited Count:14 Percentile:66.17(Materials Science, Multidisciplinary)

International Fusion Materials Irradiation Facility (IFMIF), being developed by EU, JA, RF and US, is a deuteron-lithium (Li) reaction neutron source for fusion materials testing. In the end of 2002, 3 year Key Element technology Phase (KEP) to reduce the key technology risk factors has been completed. This paper describes these KEP tasks results. To evaluate Li flow characteristics, a water and Li flow experiments have been done. To develop Li purification system, evaluation of nitrogen and tritium gettering materials have been done. Conceptual design of remote handling and basic experiment have been donde. In addition, safety analysis and diganostics design have been done. In the presentation, the latest design and future prospects will be also summarized.

Journal Articles

Penetration controlled irradiation with ion beams for biological study

; Watanabe, Hiroshi; Shimizu, Takashi*; Inoue, Masayoshi*; Kikuchi, Masahiro; Kobayashi, Yasuhiko; Tano, Shigemitsu*

Nuclear Instruments and Methods in Physics Research B, 129(1), p.42 - 48, 1997/00

 Times Cited Count:17 Percentile:77.48(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Separatrix sweeping by in-vessel coils on a fusion reactor

Nishio, Satoshi; Araki, Masanori; Shinya, K.*; Shimizu, Katsusuke*; Kuroda, Toshimasa*; Sugihara, Masayoshi; Shimomura, Yasuo

Fusion Engineering and Design, 19, p.203 - 211, 1992/00

 Times Cited Count:2 Percentile:27.5(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Japanese contributions to IAEA INTOR Workshop,Phase two A,Part 3; Chapter III; Impurity control

Mizoguchi, Tadanori*; *; Fujisawa, Noboru; Abe, Tetsuya; Hirayama, Toshio; Hitoki, Shigehisa*; *; Koide, Yoshihiko; *; *; et al.

JAERI-M 88-045, 126 Pages, 1988/03

JAERI-M-88-045.pdf:2.54MB

no abstracts in English

Oral presentation

Upgrading and achievements in the industrial analysis beamline BL05

Hasegawa, Takayuki*; Uemura, Masaharu*; Takueuchi, Kazuki*; Kodaka, Takuya*; Fukada, Noboru*; Umesaki, Norimasa*; Fukushima, Sei*; Teraoka, Yuden; Haruyama, Yuichi*; Niibe, Masahito*; et al.

no journal, , 

no abstracts in English

Oral presentation

Study of deoxidization of nitrate ion from radioactive wastewater by ultraviolet rays

Shimizu, Koki; Koyama, Hayato; Hagiwara, Masayoshi

no journal, , 

no abstracts in English

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