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JAEA Reports

Reactor safety issues resolved by 2D/3D program

JAERI 1336, 362 Pages, 1995/09

JAERI-1336.pdf:15.72MB

no abstracts in English

JAEA Reports

2D/3D program work summary report

JAERI 1335, 376 Pages, 1995/09

JAERI-1335.pdf:16.12MB

no abstracts in English

Journal Articles

Assessment of predictive capability of REFLA/TRAC code for peak clad temperature during reflood in LBLOCA of PWR with small scale test, SCTF and CCTF data

; Onuki, Akira; Murao, Yoshio

Validation of Systems Transients Analysis Codes (FED-Vol. 223), 0, 8 Pages, 1995/00

no abstracts in English

JAEA Reports

Evaluation report on SCTF-III test S3-3, S3-4 and S3-5; Counter current flow limitation phenomena in full radius core

Iguchi, Tadashi; *; Iwamura, Takamichi; ; Okubo, Tsutomu; Onuki, Akira; *; Murao, Yoshio

JAERI-M 91-172, 154 Pages, 1991/10

JAERI-M-91-172.pdf:3.19MB

no abstracts in English

JAEA Reports

JAEA Reports

Effects of radial core power profile on core thermo-hydraulic behavior during reflood phase in SCTF core-I forced feed tests

Iwamura, Takamichi; *; Sudo, Yukio; Sobajima, Makoto; Onuki, Akira; Abe, Yutaka; *; Murao, Yoshio

JAERI-M 91-093, 89 Pages, 1991/06

JAERI-M-91-093.pdf:1.87MB

no abstracts in English

JAEA Reports

Study on ECC injection modes in reflood tests with SCTF core-II; Comparison between gravity and forced feeds

Onuki, Akira; Sobajima, Makoto; Iwamura, Takamichi; *; Okubo, Tsutomu; Abe, Yutaka; Murao, Yoshio

JAERI-M 91-001, 125 Pages, 1991/02

JAERI-M-91-001.pdf:2.44MB

no abstracts in English

JAEA Reports

Comparison of facility characteristics between SCTF core-I and core-II

*; Iwamura, Takamichi; Sobajima, Makoto; Onuki, Akira; Abe, Yutaka; Murao, Yoshio

JAERI-M 90-130, 77 Pages, 1990/08

JAERI-M-90-130.pdf:1.72MB

no abstracts in English

JAEA Reports

Cold leg injection reflood test results in the SCTF core-1 under constant system pressure

Adachi, Hiromichi; Iwamura, Takamichi; Sobajima, Makoto; ; Onuki, Akira; Abe, Yutaka; Murao, Yoshio

JAERI-M 90-129, 179 Pages, 1990/08

JAERI-M-90-129.pdf:3.71MB

no abstracts in English

JAEA Reports

Implementation of an implicit method into heat conduction calculation of TRAC-PF1/MOD2 code

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

JAERI-M 90-122, 36 Pages, 1990/08

JAERI-M-90-122.pdf:0.92MB

None

JAEA Reports

Development of SCTF cold leg injection test method for eliminating U-tube oscillation during the initial period

Adachi, Hiromichi; Iwamura, Takamichi; Sobajima, Makoto; Onuki, Akira; Abe, Yutaka; Okubo, Tsutomu; Murao, Yoshio

JAERI-M 90-107, 146 Pages, 1990/07

JAERI-M-90-107.pdf:2.89MB

no abstracts in English

JAEA Reports

Reflood behavior at low initial clad temperature in slab core test facility core-II

; Okabe, Kazuharu*; Sobajima, Makoto; Abe, Yutaka; Iwamura, Takamichi; Onuki, Akira; Okubo, Tsutomu; *; Murao, Yoshio

JAERI-M 90-106, 101 Pages, 1990/07

JAERI-M-90-106.pdf:2.18MB

no abstracts in English

JAEA Reports

Analysis of SCTF/CCTF counterpart test results

Okubo, Tsutomu; Sobajima, Makoto; Iwamura, Takamichi; Onuki, Akira; Abe, Yutaka; Adachi, Hiromichi; Murao, Yoshio

JAERI-M 90-083, 155 Pages, 1990/06

JAERI-M-90-083.pdf:3.6MB

no abstracts in English

JAEA Reports

Evaluation report on SCTF core-III test S3-20; Investigation of water break-through and core cooling behaviors under intermittent ECC water delivery to upper plenum during reflood phase in PWRs with combined-injection type ECCS

Okubo, Tsutomu; Iguchi, Tadashi; Iwamura, Takamichi; ; Onuki, Akira; Abe, Yutaka; *; Adachi, Hiromichi; Murao, Yoshio

JAERI-M 90-080, 100 Pages, 1990/05

JAERI-M-90-080.pdf:2.17MB

no abstracts in English

JAEA Reports

Journal Articles

Recent study on two-dimensional thermal-hydraulic behavior in PWR core during the reflood phase of LOCA with the slab core test facility:SCTF

; ; ; ; ; Murao, Yoshio

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.2 - 104, 1986/00

no abstracts in English

Journal Articles

Initial thermal-hydraulic bebaviors under simultaneous ECC water injection into cold leg and upper plenum in a PWR-LOCA

;

Journal of Nuclear Science and Technology, 22(6), p.451 - 460, 1985/00

 Times Cited Count:1 Percentile:24.17(Nuclear Science & Technology)

no abstracts in English

28 (Records 1-20 displayed on this page)