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Journal Articles

Transient response of LWR fuels (RIA)

Udagawa, Yutaka; Fuketa, Toyoshi*

Comprehensive Nuclear Materials, 2nd Edition, Vol.2, p.322 - 338, 2020/08

Journal Articles

Reactivity control system of the high temperature engineering test reactor

Tachibana, Yukio; Sawahata, Hiroaki; Iyoku, Tatsuo; Nakazawa, Toshio

Nuclear Engineering and Design, 233(1-3), p.89 - 101, 2004/10

 Times Cited Count:10 Percentile:54.94(Nuclear Science & Technology)

no abstracts in English

Journal Articles

RAPID-L highly automated fast reactor concept without any control rods, 2; Critical experiment of lithium-6 used in LEM and LIM

Tsunoda, Hirokazu*; Sato, Osamu*; Okajima, Shigeaki; Yamane, Tsuyoshi; Iijima, Susumu; Kobe, Mitsuru*

Proceedings of International Congress on Advanced Nuclear Power Plants (ICAPP) (CD-ROM), 6 Pages, 2002/00

no abstracts in English

JAEA Reports

Outline of operation and control system and analytical investigation of transient behavior of an out-of-pile hydrogen production system for HTTR heat utilization system

Inagaki, Yoshiyuki; Hada, Kazuhiko; Nishihara, Tetsuo; Takeda, Tetsuaki; Hino, Ryutaro; Haga, Katsuhiro

JAERI-Tech 97-050, 125 Pages, 1997/10

JAERI-Tech-97-050.pdf:2.96MB

no abstracts in English

Journal Articles

Advantage of modified JAERI passive safety reactor (JPSR-II)

Murao, Yoshio; Ochiai, Masaaki

Eighth Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), 2, p.1075 - 1085, 1997/00

no abstracts in English

Journal Articles

Integrity assessment of the high temperature engineering test reactor(HTTR) control rod at very high temperatures

Tachibana, Yukio; Shiozawa, Shusaku; ; ;

Nucl. Eng. Des., 172(1-2), p.93 - 102, 1997/00

 Times Cited Count:8 Percentile:55.80(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of control rod reactivity worths for AVR power plant at cold and hot conditions

Yamashita, Kiyonobu; Murata, Isao; Shindo, Ryuichi; ; H.Werner*

Journal of Nuclear Science and Technology, 31(5), p.470 - 478, 1994/05

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Evaluation of shut down margin in scram condition for High Temperature Engineering Test Reactor(HTTR)

Murata, Isao; Yamashita, Kiyonobu; Maruyama, So; Fujimoto, Nozomu; Shindo, Ryuichi; Sudo, Yukio

JAERI-M 91-165, 71 Pages, 1991/10

JAERI-M-91-165.pdf:1.94MB

no abstracts in English

JAEA Reports

General criteria for the structural design for the HTTR control rods

Nishiguchi, Isoharu; Tachibana, Yukio; Motoki, Yasuo; Shiozawa, Shusaku

JAERI-M 90-152, 31 Pages, 1990/09

JAERI-M-90-152.pdf:0.95MB

no abstracts in English

Journal Articles

Development and valiation of nuclear design code system for High Temperature Engineering Test Reactor (HTTR)

Yamashita, Kiyonobu; Shindo, Ryuichi; Murata, Isao

The Safety,Status and Future of Non-Commercial Reactors and Irradiation Facilities,Vol. 1, p.350 - 358, 1990/09

no abstracts in English

JAEA Reports

Japanese Contributions to IAEA INTOR Workshop,Phase IIA,Part 2; Chapter XI:Concept Evolution,Chapter XII:Design Concept,and Chapter XIII:Operation and Test Programme

; ; Iida, Hiromasa; ; Seki, Masahiro; Honda, Tsutomu*; ; ; ; ; et al.

JAERI-M 85-083, 403 Pages, 1985/07

JAERI-M-85-083.pdf:8.66MB

no abstracts in English

JAEA Reports

JAEA Reports

Study of Control Rod Worth Evaluation Model for VHTR Design

Omura, Hiroshi*

JAERI-M 9433, 109 Pages, 1981/04

JAERI-M-9433.pdf:3.01MB

no abstracts in English

JAEA Reports

Design Studies for the Mark-III Core of Experimental Multi-Purpose VHTR

; ; ; ; ; ; ; Suzuki, Katsuo; ;

JAERI-M 8399, 253 Pages, 1979/08

JAERI-M-8399.pdf:5.85MB

no abstracts in English

JAEA Reports

JAEA Reports

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