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Journal Articles

Fusion reactor safety; Issues and perspective

Inabe, Teruo; Seki, Masahiro; Tsunematsu, Toshihide

Fusion Engineering and Design, 42, p.7 - 12, 1998/00

https://doi.org/10.1016/S0920-3796(98)00122-7
 Times Cited Count：5 Percentile：43.91(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Safety design requirements for nuclear fusion facilities

Inabe, Teruo

Purazuma, Kaku Yugo Gakkai-Shi, 73(8), p.812 - 819, 1997/08

https://ci.nii.ac.jp/naid/110003826915

no abstracts in English

Journal Articles

A Proposed safety assurance method and its application to the fusion experimental reactor

Okazaki, Takashi; Seki, Yasushi; Inabe, Teruo; Aoki, Isao

Fusion Engineering and Design, 30(3), p.201 - 216, 1995/07

https://doi.org/10.1016/0920-3796(94)00392-K
 Times Cited Count：1 Percentile：17.33(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

A Method of safety assurance for fusion experimental reactor

; Seki, Yasushi; Inabe, Teruo; Aoki, Isao

JAERI-M 93-112, 122 Pages, 1993/06

JAERI-M-93-112.pdf:4.05MB

no abstracts in English

JAEA Reports

Conceptual study of test reactor for fuel irradiation/reactor performance research

Inabe, Teruo; ; ; Yonomoto, Taisuke; ; Akutsu, Cho; ; Iwamura, Takamichi; Okubo, Tsutomu; Osugi, Toshitaka; et al.

JAERI-M 93-106, 104 Pages, 1993/05

JAERI-M-93-106.pdf:2.77MB

no abstracts in English

Journal Articles

Fission density in plutonium-uranium mixed oxide fuel irradiated by pulsed power in the NSRR experiments

Yanagihara, Satoshi; ; Inabe, Teruo

Journal of Nuclear Science and Technology, 26(8), p.787 - 794, 1989/08

https://doi.org/10.3327/jnst.26.787

no abstracts in English

JAEA Reports

Safety evaluation of the NSRR facility relevant to the modification for improved pulse operation and preirradiated fuel experiments

Inabe, Teruo; Terakado, Yoshibumi; Tanzawa, Sadamitsu; ; Kobayashi, Hideo

JAERI-M 88-218, 124 Pages, 1988/11

JAERI-M-88-218.pdf:3.96MB

no abstracts in English

JAEA Reports

Safety design of NSRR instrumantation and control systems for the improved pulsing operation

Inabe, Teruo; Ishijima, Kiyomi; Tanzawa, Sadamitsu; Shimazaki, Junya; Nakamura, Takehiko; ; ; ; ; ; et al.

JAERI-M 88-113, 55 Pages, 1988/06

JAERI-M-88-113.pdf:1.74MB

no abstracts in English

JAEA Reports

Development of the NSRR Digital Simulator

; Inabe, Teruo

JAERI-M 84-203, 67 Pages, 1984/11

JAERI-M-84-203.pdf:1.46MB

no abstracts in English

Journal Articles

Evaluation of effective energy deposition in test fuel during power burst experiments in NSRR

Onishi, Nobuaki; Inabe, Teruo

Journal of Nuclear Science and Technology, 19(7), p.528 - 542, 1982/00

https://doi.org/10.3327/jnst.19.528
 Times Cited Count：10 Percentile：70.90(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A study on post-accident core coolability based on practical fuel failure behaviors

; ; ; Inabe, Teruo

Nihon Genshiryoku Gakkai-Shi, 23(12), p.930 - 938, 1981/00

https://doi.org/10.3327/jaesj.23.930
 Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Results of The Preliminary Tests For Mixed Oxide Fuel Test Program at NSRR

Inabe, Teruo; ;

JAERI-M 9178, 23 Pages, 1980/11

JAERI-M-9178.pdf:1.52MB

no abstracts in English

JAEA Reports

Study on the Effects of Run-out Power on the Fuel Behavior Under RIA Conditions; LongRun-outPowerExperimentsatNSRR

; Inabe, Teruo; ; ;

JAERI-M 8285, 17 Pages, 1979/06

JAERI-M-8285.pdf:0.6MB

no abstracts in English

Journal Articles

The Nuclear safety research reactor (NSRR) in Japan

Ishikawa, Michio; Inabe, Teruo

Advances in Nuclear Science and Technology, Vol.11, p.285 - 335, 1979/00

https://doi.org/10.1007/978-1-4613-2862-9_5

no abstracts in English

Journal Articles

Fuel failure behavior of unirradiated fuel rods under reactivity initiated accident conditions

; ; ; ; ; ; Inabe, Teruo;

Nihon Genshiryoku Gakkai-Shi, 20(9), p.651 - 661, 1978/09

https://doi.org/10.3327/jaesj.20.651
 Times Cited Count：7

no abstracts in English

JAEA Reports

Quasi Steady State Multi-Demensional Space-Dependent Kinetic Code EUREKA-SPACE

Inabe, Teruo;

JAERI-M 7183, 77 Pages, 1977/08

JAERI-M-7183.pdf:2.41MB

no abstracts in English

JAEA Reports

Study on Critical Mass of UO$$_{2}$$ Fuel by Calculation with a Transport Code XSDRN

; ; ; Inabe, Teruo; ; ; ;

JAERI-M 7085, 19 Pages, 1977/05

JAERI-M-7085.pdf:0.7MB

no abstracts in English

Journal Articles

Measurement and evaluation on pulsing characteristics and experimental capability of NSRR

; Inabe, Teruo; ; ;

Journal of Nuclear Science and Technology, 14(3), p.226 - 238, 1977/03

https://doi.org/10.3327/jnst.14.226
 Times Cited Count：30

no abstracts in English

Journal Articles

Reactor Physics Characteristics of the NSRR(Nuclear Safety Research Reactor)

; Inabe, Teruo;

Nihon Genshiryoku Gakkai-Shi, 17(6), p.314 - 321, 1975/06

https://doi.org/10.3327/jaesj.17.314

no abstracts in English

19 (Records 1-19 displayed on this page)
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