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Journal Articles

Analytical study of SPERT-CDC test 859 using fuel performance codes FEMAXI-8 and RANNS

Taniguchi, Yoshinori; Udagawa, Yutaka; Amaya, Masaki

Annals of Nuclear Energy, 139, p.107188_1 - 107188_7, 2020/05

 Times Cited Count:1 Percentile:11.8(Nuclear Science & Technology)

Journal Articles

Development of plant dynamics analytical code named Conan-GTHTR for the Gas Turbine High Temperature Gas-cooled Reactor, 1; Code validation by Use of the experimental data of HTTR

Takamatsu, Kuniyoshi; Katanishi, Shoji; Nakagawa, Shigeaki; Kunitomi, Kazuhiko

Nihon Genshiryoku Gakkai Wabun Rombunshi, 3(1), p.76 - 87, 2004/03

The Gas Turbine High Temperature Reactor 300 (GTHTR300) composed of an inherent safe 600MWt reactor and a closed gas turbine power conversion system is a high efficient and economically competitive HTGR to be deployed in 2010s. To analyze the plant dynamics and the thermal hydraulics of the GTHTR300, a new analytical code (Conan-GTHTR) based on 'RELAP5/MOD3' has been developed and applied to heat transfer calculations of the High Temperature Engineering Test Reactor (HTTR) for its verification. The results proved that the new code was available for transient simulations in Higt Temperature Gas-Cooled Reactor systems.

JAEA Reports

Analytical evaluation on loss of off-site electric power simulation of the High Temperature Engineering Test Reactor

Takeda, Takeshi; Nakagawa, Shigeaki; Tachibana, Yukio; Takada, Eiji*; Kunitomi, Kazuhiko

JAERI-Research 2000-016, p.80 - 0, 2000/03

JAERI-Research-2000-016.pdf:2.72MB

no abstracts in English

JAEA Reports

JAEA Reports

Research program of the high temperature engineering test reactor for upgrading the HTGR technology

Kunitomi, Kazuhiko; Tachibana, Yukio; Takeda, Takeshi; Saikusa, Akio; Sawa, Kazuhiro

JAERI-Tech 97-030, 60 Pages, 1997/07

JAERI-Tech-97-030.pdf:2.02MB

no abstracts in English

JAEA Reports

Development of analytical code 'ACCORD' for incore and plant dynamics of high temperature gas-cooled reactor

Takeda, Takeshi; Tachibana, Yukio; Kunitomi, Kazuhiko; Itakura, Hirofumi*

JAERI-Data/Code 96-032, 147 Pages, 1996/11

JAERI-Data-Code-96-032.pdf:4.58MB

no abstracts in English

Journal Articles

Development of thermal/irradiation stress analytical code VIENUS for HTTR graphite block

Iyoku, Tatsuo; Ishihara, Masahiro; *

Journal of Nuclear Science and Technology, 28(10), p.921 - 931, 1991/10

no abstracts in English

Journal Articles

An Analysis of transients in experiments on loss-of-coolant accidents

Nuclear Science and Engineering, 60(1), p.10 - 18, 1976/01

 Times Cited Count:6

no abstracts in English

9 (Records 1-9 displayed on this page)
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