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1

Possibility of a Pressurized Water Reactor Concept with Highly Inherent Heat Removal Following Capability

ARAYA, Fumimasa, MURAO, Yoshio

Journal:

Journal of Nuclear Science and Technology

Year:

1995

Language:

english

File:

PDF, 719 KB

english, 1995

2

Transient Analysis for Design of Primary Coolant Pump Adopted to JAERI Passive Safety Reactor JPSR

ARAYA, Fumimasa, MURAO, Yoshio, IWAMURA, Takamichi

Journal:

Journal of Nuclear Science and Technology

Year:

1995

Language:

english

File:

PDF, 587 KB

english, 1995

3

Analysis of a Neutron Flux Oscillation Event at LaSalle-2

Araya, Fumimasa, Yoshida, Kazuo, Hirano, Masashi, Yabushita, Yukihisa

Journal:

Nuclear Technology

Year:

1991

Language:

english

File:

PDF, 1.42 MB

english, 1991

4

Application of PSA Methodology to Design Improvement of JAERI Passive Safety Reactor (JPSR)

IWAMURA, Takamichi, ARAYA, Fumimasa, MURAO, Yoshio

Journal:

Journal of Nuclear Science and Technology

Year:

1996

Language:

english

File:

PDF, 1.28 MB

english, 1996

5

Feasibility Study of Double-Flat-Core Type HCPWR for Reactivity Initiated Accidents.

ARAYA, Fumimasa, IWAMURA, Takamichi, OKUBO, Tsutomu, AKIMOTO, Hajime, MURAO, Yoshio

Journal:

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan

Year:

1992

File:

PDF, 4.31 MB

1992

6

Development of Three-dimensional Virtual Plant Vibration Simulator on Grid Computing Environment ITBL-IS/AEGIS

SUZUKI, Yoshio, NISHIDA, Akemi, ARAYA, Fumimasa, KUSHIDA, Noriyuki, AKUTSU, Taku, TESHIMA, Naoya, NAKAJIMA, Kohei, KONDO, Makoto, HAYASHI, Sachiko, AOYAGI, Tetsuo, NAKAJIMA, Norihiro

Journal:

Journal of Power and Energy Systems

Year:

2009

Language:

english

File:

PDF, 1.48 MB

english, 2009

7

Analysis of LaSalle-2 Neutron Flux Oscillation Event with RETRAN Code.

ARAYA, Fumimasa, HIRANO, Masashi, YOSHIDA, Kazuo, MATSUMOTO, Kiyoshi, YOKOBAYASHI, Masao, KOHSAKA, Atsuo

Journal:

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan

Year:

1992

Language:

english

File:

PDF, 6.65 MB

english, 1992

8

Status and Subjects of Thermal-hydraulic Analysis for Next-generation LWRs with Passive Safety Systems.

ARITOMI, Masanori, OHNUKI, Akira, ARAI, Kenji, KIKUTA, Michitaka, YONOMOTO, Taisuke, ARAYA, Fumimasa, AKIMOTO, Hajime

Journal:

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan

Year:

1999

File:

PDF, 10.53 MB

1999

9

A Concept of Passive Safety, Pressurized Water Reactor System with Inherent Matching Nature of Core Heat Generation and Heat Removal

MURAO, Yoshio, ARAYA, Fumimasa, IWAMURA, Takamichi, OKUMURA, Keisuke

Journal:

Journal of Nuclear Science and Technology

Year:

1995

Language:

english

File:

PDF, 1.04 MB

english, 1995

10

Development of Method to Determine Instability Threshold with RETRAN Code.

ARAYA, Fumimasa, HIRANO, Masashi, YOSHIDA, Kazuo, MATSUMOTO, Kiyoshi, YOKOBAYASHI, Masao, KOHSAKA, Atsuo

Journal:

Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan

Year:

1992

File:

PDF, 2.61 MB

1992

11

CHF Experiments under Steady-State and Transient Conditions for Tight Lattice Core with Non-Uniform Axial Power Distribution

IWAMURA, Takamichi, WATANABE, Hironori, OKUBO, Tsutomu, ARAYA, Fumimasa, MURAO, Yoshio

Journal:

Journal of Nuclear Science and Technology

Year:

1993

Language:

english

File:

PDF, 626 KB

english, 1993

12

Component-Wise Meshing Approach and Evaluation of Bonding Strategy on the Interface of Components for Assembled Finite Element Analysis of Structures

Yamada, Tomonori, Kushida, Noriyuki, Araya, Fumimasa, Nishida, Akemi, Nakajima, Norihiro

Journal:

Key Engineering Materials

Year:

2010

Language:

english

File:

PDF, 472 KB

english, 2010

13

Evaluation of PWR-LOCA under LOFT L2-3 Condition

ASAHI, Yoshiro, ARAYA, Fumimasa, WATANABE, Tadashi

Journal:

Journal of Nuclear Science and Technology

Year:

1987

Language:

english

File:

PDF, 775 KB

english, 1987

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