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JAEA Reports

Minutes of the IFMIF technical meetings; May 17-20, 2005, Tokyo, Japan

IFMIF International Team

JAERI-Review 2005-027, 416 Pages, 2005/08

JAERI-Review-2005-027.pdf:48.34MB

The International Fusion Materials Irradiation Facility (IFMIF) Technical Meetings were held on May 17-20, 2005 at Japan Atomic Energy Research Institute (JAERI) Tokyo. The main objectives were (1) to review technical status of the subsystems; accelerator, target and test facilities, (2) to technically discuss interface issues between target and test facilities, (3) to review results of peer-reviews performed in the EU and Japan, (4) to harmonize design / experimental activities among the subsystems, (5) to review and discuss the Engineering Validation and Engineering Design Activity (EVEDA) tasks, and (6) to make a report of (1) - (5) to the IFMIF Executive Subcommittee. This report presents a brief summary of the Target Technical Meeting, Test Facilities Technical Meeting, Target / Test Facilities Interface Meeting, Accelerator Technical Meeting and the Technical Integration Meeting.

JAEA Reports

Minutes of the IFMIF technical meeting; December 4-5, 2003, Kyoto, Japan

IFMIF International Team

JAERI-Review 2004-008, 219 Pages, 2004/03

JAERI-Review-2004-008.pdf:35.23MB

The IFMIF Technical Meeting was held on December 4-5, 2003 at Shiran-kaikan, Kyoto University. The main objectives are (i) to finalize the Comprehensive Design Report (CDR), (ii) to discuss IFMIF cost and organization, (iii) to review technical status of major systems, transition phase activities and EVEDA plan. This report presents a brief summary of the results of the meeting. Agenda, participants list and presentation materials are attached as Appendix.

Journal Articles

Liquid lithium target under steady state ultra high heat load of 1 GW/m$$^{2}$$ range for International Fusion Materials Irradiation Facility (IFMIF)

Nakamura, Hiroo; Ida, Mizuho*; Nakamura, Hideo; Takeuchi, Hiroshi; IFMIF International Team

Fusion Engineering and Design, 65(3), p.467 - 474, 2003/04

 Times Cited Count:4 Percentile:32.19(Nuclear Science & Technology)

IFMIF is an accelerator-based neutron source for development of fusion materials. The Li target system consists of a target assembly, a Li purification system and various diagnostics. An intense deuterium beam power up to 10 MW in a footprint of 20$$times$$5 cm$$^{2}$$ corresponds to ultra high heat flux up to 1 GW/m$$^{2}$$. To handle such an ultra high heat flux, the high-speed liquid Li flow with a velocity of 20 m/s and a concave flow configuration are necessary. According to thermal-hydraulic analysis, an induced centrifugal force (160 G) under the concave back wall of a radius of 25 cm is sufficient for IFMIF operation. To confirm the hydraulic characteristics of Li flow, water jet experiment has been done. Moreover, validation experiment in Li loop is planned. In addition, to control tritium and impurities such as C, N, O below permissible levels, a cold trap and two hot traps are used. These technologies have similarities in plasma facing components in fusion reactor. In presentation, the IFMIF Li target technology and its application of to the plasma facing component will be discussed.

JAEA Reports

IFMIF-KEP; International Fusion Materials Irradiation Facility key element technology phase report

IFMIF International Team

JAERI-Tech 2003-005, 559 Pages, 2003/03

JAERI-Tech-2003-005.pdf:48.89MB

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m$$^{2}$$, 20 dpa/y in Fe, in a volume of 500 cm$$^{3}$$ and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration.

JAEA Reports

IFMIF International Fusion Materials Irradiation Facility key element technology phase interim report

IFMIF International Team

JAERI-Tech 2002-022, 97 Pages, 2002/03

JAERI-Tech-2002-022.pdf:9.17MB

Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator- based deuteron (D+)-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m$$^{2}$$, 20 dpa/year for Fe) in a volume of 500 cm$$^{3}$$ for testing candidate fusion materials. In 2000, a 3year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test cell and design integration.

Journal Articles

Status of lithium target system for International Fusion Material Irradiation Facility (IFMIF)

Nakamura, Hiroo; Ida, Mizuho*; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki*; IFMIF International Team

Fusion Engineering and Design, 58-59, p.919 - 923, 2001/11

 Times Cited Count:9 Percentile:57.09(Nuclear Science & Technology)

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