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Journal Articles

Study of power conversion unit design of Gas Turbine High Temperature Reactor (GTHTR300)

Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Minatsuki, Isao*

Dai-31-Kai Gasu Tabin Teiki Koenkai Rombunshu, p.55 - 60, 2003/06

no abstracts in English

Journal Articles

Design study of power conversion system for the Gas Turbine High Temperature Reactor (GTHTR300)

Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Katanishi, Shoji; Kosugiyama, Shinichi; Minatsuki, Isao*; Miyoshi, Yasuyuki*

Nippon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.341 - 351, 2002/12

no abstracts in English

Journal Articles

Improvement in the design of helium turbine for the HTGR-GT power plant

Muto, Yasushi; Ishiyama, Shintaro; Inomata, Asako*; Kishibe, Tadaharu*; Minatsuki, Isao*; Matsumoto, Iwao*; Levet, F.*

Proceedings of ASME Turbo Expo 2001 (CD-ROM), 8 Pages, 2001/00

no abstracts in English

Journal Articles

High temperature engineering test reactor design

Tanaka, Toshiyuki; Shiozawa, Shusaku; ; Baba, Osamu; Minatsuki, Isao*; *; *; *

Proc. of the ASME Joint Int. Power Generation Conf., 0, 10 Pages, 1994/00

no abstracts in English

Oral presentation

Small-sized high temperature reactor (MHR-50) for electricity generation; Core design with long refueling interval

Terada, Atsuhiko; Shimakawa, Satoshi; Shibata, Taiju; Shiozawa, Shusaku*; Minatsuki, Isao

no journal, , 

High Temperature Gas-cooled Reactor (HTGR) has several features different from conventional light water reactors such as high passive safety characteristics, high thermal efficiency and high economy for small sized reactor with modular concept. On the other hand, one of disadvantages of HTGR with prismatic core is to require rather long-term and expensive refueling, resulting in relatively high maintenance period and cost. To solve the disadvantage, the present study challenges the core design of MHR-50 for long refueling interval by increasing core size, fuel loading and fuel burn-up. The preliminary burn-up calculation suggested that approximately 10 years of long refueling interval was found to be reasonably achieved.

Oral presentation

Design study of small-sized high temperature gas-cooled reactor (MHR-50/100is), 4; Study for core physics and safety

Nakagawa, Shigeaki; Kunitomi, Kazuhiko; Tachibana, Yukio; Terada, Atsuhiko; Minatsuki, Isao*; Oyama, Sunao*; Tsukamoto, Hiroki*

no journal, , 

no abstracts in English

Oral presentation

Design study of small-sized high temperature gas-cooled reactor (MHR-50/100is), 1; Outline of development of small-sized high temperature gas-cooled reactor concept

Shimizu, Katsusuke*; Minatsuki, Isao*; Otani, Tomomi*; Mizokami, Yoritaka*; Oyama, Sunao*; Tsukamoto, Hiroki*; Kunitomi, Kazuhiko; Tachibana, Yukio; Terada, Atsuhiko

no journal, , 

no abstracts in English

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