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Journal Articles

Feasible approach to the power reactor concept

Nishio, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.944 - 948, 2004/11

Low aspect ratio tokamak power reactor with super-conducting toroidal field (TF) coils has been proposed. A center solenoid coil system and an inboard blanket were removed. The key point was how to find the engineering design solution of the TF coil system with the high field and high current density. The coil system with the center post radius of less than 1 m can generate the maximum field of $$sim$$ 20 T. This coil system causes a compact reactor concept, where the plasma major and minor radii of 3.5 m and 1.5 m, respectively and the fusion power of $$sim$$ 3 GW.

Journal Articles

Preliminary design of 600MWt HTGR-gas turbine plant

; Miyamoto, Yoshiaki; Shiozawa, Shusaku

Proceedings of 7th International Conference on Nuclear Engineering (ICONE-7) (CD-ROM), 10 Pages, 1999/00

no abstracts in English

JAEA Reports

None

Kato, Masato

PNC-TN8600 94-005, 132 Pages, 1994/08

PNC-TN8600-94-005.pdf:7.95MB

no abstracts in English

JAEA Reports

None

Kato, Masato

PNC-TN8600 94-004, 184 Pages, 1994/08

PNC-TN8600-94-004.pdf:9.48MB

no abstracts in English

Journal Articles

Macroscopic calculational model of fission gas release from water reactor fuels

Uchida, Masaaki

Journal of Nuclear Science and Technology, 30(8), p.752 - 761, 1993/08

 Times Cited Count:2 Percentile:68.67(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Recent progress and future prospects of the JT-60 Program

Ninomiya, Hiromasa; JT-60 Team

15th IEEE/NPSS Symp. on Fusion Engineering,Vol. 2, 0, p.779 - 787, 1993/00

no abstracts in English

JAEA Reports

Test apparatus for ITER blanket cooling water distributor design

Yoshida, Hiroshi; Enoeda, Mikio; Hirata, Shingo*; Ito, H.*

JAERI-M 92-070, 45 Pages, 1992/05

JAERI-M-92-070.pdf:1.34MB

no abstracts in English

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