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JAEA Reports

Effect of ship motions and flow stability in a small marine reactor driven by natural circulation

Yoritsune, Tsutomu; Ishida, Toshihisa

JAERI-Research 2001-053, 45 Pages, 2001/12

JAERI-Research-2001-053.pdf:1.77MB

no abstracts in English

JAEA Reports

Steady-state and transient DNB analyses for JAERI passive safety reactor (JPSR) using COBRA-IV-I and RETRAN-02/Mod3 codes

Okubo, Tsutomu; X.Jiang*; Araya, Fumimasa; Ochiai, Masaaki

JAERI-Research 98-042, 49 Pages, 1998/08

JAERI-Research-98-042.pdf:1.58MB

no abstracts in English

Journal Articles

Transient analysis for design of primary coolant pump adopted to JAERI passive safety reactor JPSR

Araya, Fumimasa; Murao, Yoshio; Iwamura, Takamichi

Journal of Nuclear Science and Technology, 32(10), p.1039 - 1046, 1995/10

https://doi.org/10.3327/jnst.32.1039
 Times Cited Count：5 Percentile：49.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Effects by sea wave on thermal hydraulics of marine reactor system

Ishida, Toshihisa; Kusunoki, Tsuyoshi; ; *; Inoue, Kimio*

Journal of Nuclear Science and Technology, 32(8), p.740 - 751, 1995/08

https://doi.org/10.3327/jnst.32.740
 Times Cited Count：33 Percentile：93.13(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Possibility of a pressurized water reactor concept with highly inherent heat removel following capability

Araya, Fumimasa; Murao, Yoshio

Journal of Nuclear Science and Technology, 32(4), p.339 - 350, 1995/04

https://doi.org/10.3327/jnst.32.339
 Times Cited Count：3 Percentile：36.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of method to determine instability threshold with RETRAN code

Araya, Fumimasa; Hirano, Masashi; ; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo

Nihon Genshiryoku Gakkai-Shi, 34(9), p.879 - 888, 1992/09

https://doi.org/10.3327/jaesj.34.879
 Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analysis of LaSalle-2 neutron flux oscillation event with RETRAN code

Araya, Fumimasa; Hirano, Masashi; ; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo

Nihon Genshiryoku Gakkai-Shi, 34(6), p.565 - 575, 1992/06

https://doi.org/10.3327/jaesj.34.565
 Times Cited Count：1 Percentile：17.24(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Development of analysis code for thermal hydro-dynamics of marine reactor under multi-dimensional ship motions, RETRAN-02/GRAV; Improvement of RETRAN-02 and experimental analysis

Ishida, Toshihisa; *

JAERI-M 91-226, 129 Pages, 1992/01

JAERI-M-91-226.pdf:3.32MB

no abstracts in English

Journal Articles

Analysis of a neutron flux oscillation event at LaSalle-2

Araya, Fumimasa; ; Hirano, Masashi; *

Nuclear Technology, 93, p.82 - 91, 1991/01

https://doi.org/10.13182/NT91-A34520
 Times Cited Count：11 Percentile：74.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Thermal hydro-dynamics behavior of the nuclear-powered ship MUTSU in the power-up test

Ishida, Toshihisa; Kusunoki, Tsuyoshi; *; *; Inoue, Kimio*; ;

Proc. of the lst JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.521 - 526, 1991/00

no abstracts in English

Journal Articles

Analysis of neutron flux oscillation event at LaSalle 2

Araya, Fumimasa; ; Hirano, Masashi; *

EPRI-NP-6949, p.22-1 - 22-23, 1990/08

no abstracts in English

Journal Articles

Summary of RETRAN calculations on LaSalle 2 neutron flux oscillation event performed at JAERI

Araya, Fumimasa; Hirano, Masashi; ; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo

CSNI-178, p.370 - 384, 1990/00

no abstracts in English

Journal Articles

Parametric study on neutron flux oscillation event at LaSalle 2 with RETRAN code

Araya, Fumimasa; ; Hirano, Masashi; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo

ANS Proc. on 1989 National Heat Transfer Conf., Vol. 4, p.69 - 76, 1989/00

no abstracts in English

Journal Articles

Thermal-Hydraulic Behaviors during a loss of offsite power transient without SCRAM of a PWR

; ; ; ; ;

Nihon Genshiryoku Gakkai-Shi, 28(11), p.1045 - 1055, 1986/11

https://doi.org/10.3327/jaesj.28.1045
 Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Core meltdown accident analysis for a BWR plant with MARK I type containment

; ; ; *; *

Source Term Evaluation for Accident Conditions, p.733 - 744, 1986/00

no abstracts in English

JAEA Reports

Safety Analysis of Upgranded JRR-3 by RETRAN-02RR Code(Part2) (Analysis of Operational Tramgents and Accodents)

; ; *; *; *;

JAERI-M 84-218, 157 Pages, 1984/12

JAERI-M-84-218.pdf:3.12MB

no abstracts in English

JAEA Reports

Safety Analysis of Upgranded JRR-3 by RETRAN-02/RR Code (Part1) (Development of Safety Analysis Code for Reserch Reactor)

; ; *; *; *; *

JAERI-M 84-217, 97 Pages, 1984/12

JAERI-M-84-217.pdf:2.08MB

no abstracts in English

JAEA Reports

An Evaluation of The RETRAN Code Upon ATWS Accident Analysis in A BWR

JAERI-M 82-168, 41 Pages, 1982/11

JAERI-M-82-168.pdf:0.91MB

no abstracts in English

JAEA Reports

PWRDYN;A Computer Code for PWR Plant Dynamic Analysis

JAERI-M 82-064, 61 Pages, 1982/06

JAERI-M-82-064.pdf:1.48MB

no abstracts in English

JAEA Reports

Safety Analysis on the Operational Transients and some Accidents of MUTSU Reactor

;

JAERI-M 9398, 147 Pages, 1981/03

JAERI-M-9398.pdf:3.1MB

no abstracts in English

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