Refine your search:     
Report No.
 - 
Search Results: Records 1-9 displayed on this page of 9
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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:66.93(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.

Journal Articles

Parametric enhancement of the tunneling transmission through a potential barrier

; *

Journal of Nuclear Science and Technology, 29(12), p.1129 - 1132, 1992/12

no abstracts in English

Journal Articles

Cryogenic system design and its component development for Fusion Experimental Reactor(FER)

Kato, Takashi; Tada, Eisuke; Hiyama, Tadao; Kawano, Katsumi; *; *; *; *; Shimamoto, Susumi

Fusion Technology 1990, p.1535 - 1539, 1991/00

no abstracts in English

Journal Articles

Electrochemical calorimetry of D$$_{2}$$O electrolysis using a palladium cathode; An Undivided, open cell system

*; *; *; *; *; *; *; Oyama, Yukio; Nakamura, Tomoo; Shibata, Tokushi*; et al.

Bulletin of the Chemical Society of Japan, 63(9), p.2659 - 2664, 1990/09

 Times Cited Count:1 Percentile:84.03(Chemistry, Multidisciplinary)

no abstracts in English

JAEA Reports

Record of Forum on Cold Fusion

Shikazono, Naomoto; Tachikawa, Enzo;

JAERI-M 89-132, 40 Pages, 1989/09

JAERI-M-89-132.pdf:1.14MB

no abstracts in English

Journal Articles

Fractofusion mechanism

; Takizuka, Tomonori

Journal of the Physical Society of Japan, 58(9), p.3073 - 3076, 1989/09

 Times Cited Count:17 Percentile:20.44(Physics, Multidisciplinary)

no abstracts in English

JAEA Reports

Fracto-fusion; Mechanism of cold fusion

; Takizuka, Tomonori

JAERI-M 89-093, 16 Pages, 1989/07

JAERI-M-89-093.pdf:0.47MB

no abstracts in English

JAEA Reports

Numerical Studies on JT-60 Divertor Plasma Characteristics

Yoshida, H.; ;

JAERI-M 86-008, 54 Pages, 1986/02

JAERI-M-86-008.pdf:1.33MB

no abstracts in English

9 (Records 1-9 displayed on this page)
  • 1