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Journal Articles

Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions

Marian, J.*; Becquart, C. S.*; Domain, C.*; Dudarev, S. L.*; Gilbert, M. R.*; Kurtz, R. J.*; Mason, D. R.*; Nordlund, K.*; Sand, A. E.*; Snead, L. L.*; et al.

Nuclear Fusion, 57(9), p.092008_1 - 092008_26, 2017/06

 Times Cited Count:104 Percentile:99.25(Physics, Fluids & Plasmas)

Under the anticipated operating conditions for demonstration magnetic fusion reactors beyond ITER, structural materials will be exposed to unprecedented conditions of irradiation, heat flux, and temperature. While such extreme environments remain inaccessible experimentally, computational modeling and simulation can provide qualitative and quantitative insights into materials response and complement the available experimental measurements. For plasma facing components such as the first wall and the divertor, tungsten (W) has been selected as the best candidate material due to its superior high-temperature and irradiation properties. In this paper we provide a review of recent efforts in computational modeling of W both as a plasma-facing material as well as a bulk structural material subjected to fast neutron irradiation. We highlight several of the most salient findings obtained via computational modeling and point out a number of remaining future challenges.

Journal Articles

Present status of the high current prototype accelerator for IFMIF/EVEDA

Okumura, Yoshikazu

Proceedings of 11th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.194 - 198, 2014/10

International Fusion Materials Irradiation Facility (IFMIF) is one of the major facilities in fusion program to irradiate and characterize the fusion materials under intense neutron field. Under the framework of Broader Approach (BA) agreement between Japan and Euratom, Engineering Validation and Engineering Design Activities (EVEDA) launched in 2007 in Japan to validate the key technologies to realize IFMIF. The most critical technology to realize IFMIF is two set of linear accelerators each producing 125mA/CW deuterium ion beams up to 40MeV. The prototype accelerator being developed in EVEDA consists of an injector, a RFQ accelerator, and a superconducting linac, whose target is to produce 125mA/CW deuterium ion beams up to 9MeV. The injector has been delivered to International Fusion Energy Research Center (IFERC) in Rokkasho, Japan, where all the accelerator components will be assembled and operated to validate the accelerator technologies required for IFMIF.

Journal Articles

Designs of contraction nozzle and concave back-wall for IFMIF target

Ida, Mizuho*; Nakamura, Hideo; Nakamura, Hiroo; Takeuchi, Hiroshi

Fusion Engineering and Design, 70(2), p.95 - 106, 2004/02

 Times Cited Count:18 Percentile:74.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Water jet flow simulation and lithium free surface flow experiments for the IFMIF target

Ida, Mizuho*; Horiike, Hiroshi*; Akiba, Masato; Ezato, Koichiro; Iida, Toshiyuki*; Inoue, Shoji*; Miyamoto, Seiji*; Muroga, Takeo*; Nakamura, Hideo; Nakamura, Hiroshi*; et al.

Journal of Nuclear Materials, 307-311(Part2), p.1686 - 1690, 2002/12

 Times Cited Count:6 Percentile:39.54(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Tritium processing and tritium laboratory in International Fusion Materials Irradiation Facility (IFMIF)

Yutani, Toshiaki*; Nakamura, Hiroo; Sugimoto, Masayoshi; Takeuchi, Hiroshi

Fusion Science and Technology, 41(3), p.850 - 853, 2002/05

no abstracts in English

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:56.08(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Reduced cost design of liquid lithium target for International Fusion Material Irradiation Facility (IFMIF)

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

JAERI-Tech 2000-078, 17 Pages, 2001/01

JAERI-Tech-2000-078.pdf:1.93MB

no abstracts in English

Journal Articles

Staged deployment of the international fusion materials irradiation facility (IFMIF)

Takeuchi, Hiroshi; Sugimoto, Masayoshi; Nakamura, Hiroo; Yutani, Toshiaki*; Ida, Mizuho*; Jitsukawa, Shiro; Kondo, Tatsuo; Matsuda, Shinzaburo; Matsui, Hideki*; Shannon, T. E.*; et al.

Fusion Energy 2000 (CD-ROM), 5 Pages, 2001/00

no abstracts in English

JAEA Reports

IFMIF international fusion materials irradiation facility key element technology phase task description

Fusion Neutron Laboratory

JAERI-Tech 2000-052, 110 Pages, 2000/08

JAERI-Tech-2000-052.pdf:5.31MB

no abstracts in English

Journal Articles

Development of high intensity deuteron ion source for fusion intense neutron source

Kinsho, Michikazu; Sugimoto, Masayoshi; Seki, Masakazu; Oguri, Hidetomo; Okumura, Yoshikazu

Review of Scientific Instruments, 71(2), p.963 - 965, 2000/02

 Times Cited Count:1 Percentile:20.05(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Thermal-hydraulic analysis of liquid lithium target for international fusion materials irradiatioin facility (IFMIF)

Ida, Mizuho*; Nakamura, Hideo; Nakamura, Hiroo; Takeuchi, Hiroshi

Proceedings of Japan-US Workshop on High Heat Flux Components and Plasma Surface Interactions for Next Fusion Devices, p.59 - 68, 2000/00

no abstracts in English

Journal Articles

International Fusion Materials Irradiation Facility conceptual Design Activity; Present status and perspective

Katsuta, Hiroji; Noda, Kenji; ; Sugimoto, Masayoshi; Maekawa, Hiroshi; Konishi, Satoshi; Nakamura, Hideo; *; Oyama, Yukio; Jitsukawa, Shiro; et al.

Nihon Genshiryoku Gakkai-Shi, 40(3), p.162 - 191, 1998/00

no abstracts in English

Journal Articles

Fluid stability analysis for IFMIF target

*; ; Nakamura, Hideo; Takeuchi, Hiroshi; D.Tirelli*; S.Cevolani*

Proc. of 2nd Int. Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp'98), p.548 - 555, 1998/00

no abstracts in English

JAEA Reports

Safety design of the international fusion materials irradiation facility (IFMIF)

Konishi, Satoshi; Yamaki, Daiju; Katsuta, Hiroji; M$"o$slang, A.*; R.Jameson*; Martone, M.*; Shannon, T. E.*

JAERI-Tech 97-056, 9 Pages, 1997/11

JAERI-Tech-97-056.pdf:0.63MB

no abstracts in English

Journal Articles

Thermal and fluid analysis for the IFMIF lithium target jet flow

*; Nakamura, Hideo; *; ; Maekawa, Hiroshi

Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 3, p.1276 - 1283, 1997/00

no abstracts in English

Journal Articles

Accelerator conceptual design of the international fusion materials irradiation facility (IFMIF)

Sugimoto, Masayoshi

Proc. of the 20th Linear Accelerator Meeting in Japan, 0, p.97 - 99, 1995/00

no abstracts in English

Journal Articles

The Status and prospects of high-energy neutron test facilities for fusion materials development

Kondo, Tatsuo; D.G.Doran*; K.Ehrlich*; F.W.Wiffen*

Journal of Nuclear Materials, 191-194, p.100 - 107, 1992/00

no abstracts in English

Journal Articles

Outline of TIARA

Tanaka, Ryuichi

Hoshasen To Sangyo, (52), p.34 - 39, 1991/12

no abstracts in English

Journal Articles

Plan of ion beam application in JAERI, Takasaki

Tanaka, Ryuichi

Nihon Genshiryoku Gakkai-Shi, 33(11), p.1018 - 1023, 1991/11

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

*; Miyakawa, Shunichi; Koyama, Masahiro

PNC TN9440 87-007, 58 Pages, 1987/10

PNC-TN9440-87-007.pdf:1.75MB

None

30 (Records 1-20 displayed on this page)