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JAEA Reports

Design of High Temperature Engineering Test Reactor (HTTR)

Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; Shindo, Masami; Shiozawa, Shusaku; Mogi, Haruyoshi; Okubo, Minoru; Ito, Noboru; Shindo, Ryuichi; et al.

JAERI 1332, 247 Pages, 1994/09

JAERI-1332.pdf:11.53MB

no abstracts in English

Journal Articles

Progress of research and development in Japan Atomic Energy Research Institute

Saito, Shinzo

Denki Hyoron, 0(2), p.57 - 63, 1994/02

no abstracts in English

JAEA Reports

Color temperature evaluation in fuel behavior observation tests in NSRR

Nakamura, Takehiko; Saito, Shinzo; Emori, Yasubumi*; Namba, Hisao*;

JAERI-M 93-068, 37 Pages, 1993/03

JAERI-M-93-068.pdf:3.09MB

no abstracts in English

Journal Articles

Current status of HTTR development and heat application test

Saito, Shinzo

Gensan Semina "Koon Gasuro Kaihatsu To Netsu Riyo Gijutsu No Tembo", p.1 - 10, 1992/02

no abstracts in English

Journal Articles

Estimation of 「nuclear energy」 in mid-21st century high temperature gas-cooled reactor

Saito, Shinzo

Genshiryoku Kogyo, 38(1), p.24 - 30, 1992/01

no abstracts in English

Journal Articles

Design concept and construction status of HTTR

Saito, Shinzo; Sudo, Yukio; Tanaka, Toshiyuki; Baba, Osamu

91-JPGC-NE-16, 8 Pages, 1991/00

no abstracts in English

Journal Articles

Present status of HTGR development program in Japan

Saito, Shinzo

Energy, 16(1-2), p.129 - 136, 1991/00

 Times Cited Count:0 Percentile:0.03(Thermodynamics)

no abstracts in English

Journal Articles

Design and safety consideration in the High-Temperature Engineering Test Reactor(HTTR)

Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; Shiozawa, Shusaku; Okubo, Minoru

Energy, 16(1-2), p.449 - 458, 1991/00

 Times Cited Count:4 Percentile:55.43(Thermodynamics)

no abstracts in English

Journal Articles

Analytical method and result of off-site exposure during normal operation of High Temperature Engineering Test Reactor(HTTR)

Sawa, Kazuhiro; *; Saito, Shinzo

Energy, 16(1-2), p.459 - 470, 1991/00

 Times Cited Count:9 Percentile:69.57(Thermodynamics)

no abstracts in English

Journal Articles

Present status of the High Temperature Engineering Test Reactor(HTTR)

Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio

Nucl. Eng. Des., 132, p.85 - 93, 1991/00

 Times Cited Count:19 Percentile:87.27(Nuclear Science & Technology)

no abstracts in English

Journal Articles

High-Temperature Gas-cooled Reactors (HTGRs) and their potential for non-electric application

Saito, Shinzo

Proc. of IEA Int. Conf. on Technology Responses to Global Environmental Challenges,Vol. l, p.393 - 396, 1991/00

no abstracts in English

Journal Articles

Determination of hot spot factors for thermal and hydraulic design of High Temperature Engineering Test Reactor (HTTR)

Maruyama, So; Murakami, Tomoyuki*; Fujii, Sadao*; Fujimoto, Nozomu; Tanaka, Toshiyuki; Sudo, Yukio; Saito, Shinzo

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.425 - 430, 1991/00

no abstracts in English

Journal Articles

Safety requirements and research and development on HTTR fuel

Saito, Shinzo; Shiozawa, Shusaku; Fukuda, Kosaku; Kondo, Tatsuo

Proc. of the Behaviour of Gas Cooled Reactor Fuel Under Accident Conditions, p.31 - 36, 1991/00

no abstracts in English

Journal Articles

High temperature gas-cooled reactor and its applications

Saito, Shinzo

Sekiyu Gakkai-Shi, 34(6), p.486 - 499, 1991/00

no abstracts in English

Journal Articles

Design of High Temperature Engineering Test Reactor(HTTR) and associated resarch and development

Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; ; Hishida, Makoto; ; ; Shinohara, Yoshikuni; *; et al.

Nihon Genshiryoku Gakkai-Shi, 32(9), p.847 - 871, 1990/09

no abstracts in English

Journal Articles

High temperature gas-cooled reactor to be paid attention now; Its present status and perspective

Saito, Shinzo; Sudo, Yukio; Fukuda, Kosaku; Nakajima, Hajime; Oku, Tatsuo; ; Tanaka, Toshiyuki

Genshiryoku Kogyo, 36(4), p.20 - 62, 1990/04

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

Journal Articles

Present status of HTTR project in Japan

Tanaka, Toshiyuki; Saito, Shinzo

Juel-Conf-71, p.33 - 47, 1989/04

no abstracts in English

JAEA Reports

Study on the behavior of Gd$$_{2}$$O$$_{3}$$ fuel rod failure under a reactivity initiated accident

Shiozawa, Shusaku; Saito, Shinzo; ; *; *; Takeda, M.*; *; *; *

JAERI-M 88-084, 47 Pages, 1988/05

JAERI-M-88-084.pdf:2.11MB

no abstracts in English

Journal Articles

Present status of high temperature gus-cooled reactor development

Sanokawa, Konomo; Saito, Shinzo

Nihon Genshiryoku Gakkai-Shi, 29(7), p.603 - 613, 1987/07

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

59 (Records 1-20 displayed on this page)