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Journal Articles

Application of the GIF safety design criteria and safety design guidelines on passive reactor shutdown capability to next generation sodium-cooled fast reactor in Japan

Yamano, Hidemasa; Futagami, Satoshi; Sasa, Kyohei*; Nakamura, Hironori*; Tokizaki, Minako*; Kubota, Ryuzaburo*

Proceedings of 2025 International Congress on Advances in Nuclear Power Plants (ICAPP 2025) (Internet), 12 Pages, 2025/09

This study examined the application of safety design criteria (SDC) and safety design guideline (SDG) developed in the Generation-IV international forum on the passive reactor shutdown capability to sodium-cooled fast reactors (SFRs) recently designed in Japan.

Journal Articles

Application of the GIF safety design criteria and safety design guidelines on reactor shutdown system to next generation sodium-cooled fast reactor in Japan

Yamano, Hidemasa; Futagami, Satoshi; Shibata, Akihiro*

Proceedings of Advanced Reactor Safety (ARS 2024), p.151 - 160, 2024/08

This study examined the application of safety design criteria (SDC) and safety design guideline (SDG) developed in the Generation-IV international forum on the active reactor shutdown system (RSS) to sodium-cooled fast reactors (SFRs) recently designed in Japan.

Journal Articles

Safety shutdown of the High Temperature Engineering Test Reactor during loss of off-site electric power simulation test

Takeda, Takeshi; Nakagawa, Shigeaki; Homma, Fumitaka*; Takada, Eiji*; Fujimoto, Nozomu

Journal of Nuclear Science and Technology, 39(9), p.986 - 995, 2002/09

 Times Cited Count:6 Percentile:33.15(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Cool-down, static heat load and warm-up performance of the central solenoid model coil and the central solenoid insert model coil

Hara, Eiji*; Hamada, Kazuya; Kawano, Katsumi; Kato, Takashi; Shimba, Toru*; CS Model Coil Test Group

Teion Kogaku, 36(6), p.324 - 329, 2001/06

no abstracts in English

Journal Articles

Test results of the SMES model coil; Cool-down and thermal characteristics

Hamada, Kazuya; Kato, Takashi; Kawano, Katsumi; ; ; ; Imahashi, Koichi*; Otsu, K.*; Tajiri, F.*; Ouchi, T.*; et al.

Teion Kogaku, 33(7), p.467 - 472, 1998/00

no abstracts in English

JAEA Reports

Cool-down simulation of Nb$$_{3}$$Al insert after dumping for coil protection

; Koizumi, Norikiyo; Ando, Toshinari; Tsuji, Hiroshi; Kuchiishi, Yoshikazu*; Asano, Katsuhiko*

JAERI-Research 97-044, 10 Pages, 1997/07

JAERI-Research-97-044.pdf:0.58MB

no abstracts in English

Journal Articles

Terminating core boiling by hot-leg injection in cold-leg small-break LOCA

Kumamaru, Hiroshige; Kukita, Yutaka

Int. Conf. on New Trends in Nuclear System Thermohydraulics,Vol. 1, 0, p.119 - 126, 1994/00

no abstracts in English

Journal Articles

Experimental study of differences in CHF between upflow and downflow in vertical rectangular channels; Effect of subcooling

Kaminaga, Masanori; Sudo, Yukio

Nihon Kikai Gakkai Rombunshu, B, 58(553), p.2799 - 2804, 1993/09

no abstracts in English

Journal Articles

A New CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors

Sudo, Yukio; Kaminaga, Masanori

J. Heat Transfer, 115, p.426 - 434, 1993/05

 Times Cited Count:68 Percentile:94.17(Thermodynamics)

no abstracts in English

Journal Articles

Quasi-static core liquid level depression and long-term core uncovery during a PWR LOCA

Kukita, Yutaka; R.R.Schultz*; Nakamura, Hideo; Katayama, Jiro*

Nucl. Saf., 34(1), p.33 - 48, 1993/01

no abstracts in English

Journal Articles

Test results of the DPC-TJ; Thermal and hydraulic performances

Sugimoto, Makoto; Kato, Takashi; Kawano, Katsumi; Hiyama, Tadao; ; ; ; ; ; Okuno, Kiyoshi; et al.

Teion Kogaku, 27(3), p.239 - 244, 1992/00

no abstracts in English

Journal Articles

A New CHF correlation scheme proposed for vertical rectangular channels heated from both sides in nuclear research reactors

Kaminaga, Masanori; Sudo, Yukio

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.73 - 79, 1991/00

no abstracts in English

Journal Articles

Experimental study of incipient nucleate boiling in narrow vertical rectangular channel simulating subchannel of upgraded JRR-3

Sudo, Yukio; ; ; Kaminaga, Masanori

Journal of Nuclear Science and Technology, 23(1), p.73 - 82, 1985/00

 Times Cited Count:39 Percentile:94.89(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Parameter effects on downcomer penetration of ECC water in a PWR-LOCA

Sudo, Yukio

Journal of Nuclear Science and Technology, 21(1), p.32 - 41, 1984/00

 Times Cited Count:2 Percentile:29.47(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Design of Slab Core Test Facility(SCTF)in Large Scale Reflood Test Pprogram,Part I :Core-I

; Sudo, Yukio; ; ; ; ; ; ; ; Osakabe, Masahiro; et al.

JAERI-M 83-080, 171 Pages, 1983/06

JAERI-M-83-080.pdf:3.9MB

no abstracts in English

JAEA Reports

System Pressure Effects on Reflooding Phenomena Observed in the SCTF Core-I Forced Flooding Tests

; Sudo, Yukio; ; ; Osakabe, Masahiro; ; Abe, Yutaka

JAERI-M 83-079, 116 Pages, 1983/06

JAERI-M-83-079.pdf:2.28MB

no abstracts in English

JAEA Reports

Re-Analysis of CSNI Standard Problem No.8

;

JAERI-M 9842, 68 Pages, 1981/12

JAERI-M-9842.pdf:1.72MB

no abstracts in English

JAEA Reports

Subcooled Decompression Analysis of LOFT L1-3A Test Data with Digital Computer Code DEPCO-MULTI

; ; Soda, Kunihisa

JAERI-M 7173, 18 Pages, 1977/07

JAERI-M-7173.pdf:0.44MB

no abstracts in English

JAEA Reports

24 (Records 1-20 displayed on this page)