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Journal Articles

Neutronic and thermal estimation of blanket in-pile mockup with Li$$_{2}$$TiO$$_{3}$$ pebbles

Nagao, Yoshiharu; Nakamichi, Masaru; Tsuchiya, Kunihiko; Kawamura, Hiroshi

Fusion Engineering and Design, 58-59, p.673 - 678, 2001/11

https://doi.org/10.1016/S0920-3796(01)00525-7
 Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Verification of in-core thermal and hydraulic analysis code FLOWNET/TRUMP for the High Temperature Engineering Test Reactor(HTTR) at JAERI

Maruyama, So; Sudo, Yukio; Saito, Shinzo; Kiso, Yoshihiro*; *

Proc. of the 4th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Vol. 1, p.227 - 232, 1989/12

no abstracts in English

JAEA Reports

Computation of Irradiation Temperature in Fuel Rods of OGL-1 Fuel Assembly

; ; Minato, Kazuo; Ikawa, Katsuichi; Iwamoto, K.

JAERI-M 84-183, 39 Pages, 1984/10

JAERI-M-84-183.pdf:1.14MB

no abstracts in English

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