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Journal Articles

Study of accident management measures for prevention of severe core damage in ROSA-V program

Asaka, Hideaki; Anoda, Yoshinari

Konsoryu, 17(2), p.116 - 125, 2003/06

no abstracts in English

Journal Articles

Design of advanced integral-type marine reactor, MRX

Kusunoki, Tsuyoshi; Odano, Naoteru; Yoritsune, Tsutomu; Ishida, Toshihisa; Hoshi, Tsutao*; Sako, Kiyoshi*

Nuclear Engineering and Design, 201(2-3), p.155 - 175, 2000/10

 Times Cited Count:56 Percentile:93.58(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Effect of fuel assembly configuration and fuel rod configuration on thermal-hydraulic behavior in core during reflood phase of PWR-LOCA

Onuki, Akira; ; Iguchi, Tadashi; Murao, Yoshio

JAERI-Research 94-012, 59 Pages, 1994/08

JAERI-Research-94-012.pdf:1.75MB

no abstracts in English

JAEA Reports

Improvement of pressure drop caluculation model in TRAC-PF1 code

; Abe, Yutaka*; Onuki, Akira; Murao, Yoshio

JAERI-Data/Code 94-006, 40 Pages, 1994/07

JAERI-Data-Code-94-006.pdf:1.26MB

no abstracts in English

Journal Articles

Shielding design of obtain compact marine reactor

;

Journal of Nuclear Science and Technology, 31(6), p.510 - 520, 1994/06

 Times Cited Count:24 Percentile:85.62(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Journal Articles

Development of software integration methodology for human-friendly and intelligent nuclear reactor design support system

Araya, Fumimasa; ; ; ;

Proc. of the Joint Int. Conf. on Mathematical Methods and Supercomputing in Nuclear Applications,Vol. 1, p.466 - 476, 1993/00

no abstracts in English

JAEA Reports

Thermal-hydraulic study of a High Conversion Light Water Reactor

JAERI-M 91-055, 198 Pages, 1991/03

JAERI-M-91-055.pdf:4.4MB

no abstracts in English

JAEA Reports

Conceptual design of the advanced marine reactor MRX

JAERI-M 91-004, 532 Pages, 1991/02

JAERI-M-91-004.pdf:13.82MB

no abstracts in English

Journal Articles

Effect of pressure drop through broken cold leg on thermal hydraulic behavior during reflood phase of PWR-LOCA

; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 25(1), p.45 - 55, 1988/01

no abstracts in English

Journal Articles

Hydrodynamics of ECC water bypass and refill of lower plenum at PWR-LOCA

; Murao, Yoshio

Journal of Nuclear Science and Technology, 24(10), p.785 - 797, 1987/10

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

no abstracts in English

Journal Articles

Core radial power profile effect on system and core cooling behavior during reflood phase of PWR-LOCA with CCTF data

; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 22(7), p.538 - 550, 1985/00

 Times Cited Count:12 Percentile:79.68(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Swelling model of two-phase mixture in lower plenum at end of blowdown phase of PWR-LOCA

; Murao, Yoshio

Journal of Nuclear Science and Technology, 21(12), p.919 - 930, 1984/00

 Times Cited Count:2 Percentile:29.43(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Pressure drop through broken cold leg during reflood phase of loss-of-coolant accident of pressurized water reactor

; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 21(6), p.450 - 465, 1984/00

 Times Cited Count:6 Percentile:56.49(Nuclear Science & Technology)

no abstracts in English

14 (Records 1-14 displayed on this page)
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