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Journal Articles

Estimation of long-term ex-vessel debris cooling behavior in Fukushima Daiichi Nuclear Power Plant unit 3

Sato, Ikken; Yamaji, Akifumi*; Li, X.*; Madokoro, Hiroshi

Mechanical Engineering Journal (Internet), 9(2), p.21-00436_1 - 21-00436_17, 2022/04

Journal Articles

An Interpretation of Fukushima-Daiichi Unit 3 plant data covering the two-week accident-progression phase based on correction for pressure data

Sato, Ikken

Journal of Nuclear Science and Technology, 56(5), p.394 - 411, 2019/05

 Times Cited Count:5 Percentile:75.46(Nuclear Science & Technology)

Water columns were adopted in the pressure measurement system of Fukushima-Daiichi Unit-3. Part of these water columns evaporated during the accident condition jeopardizing correct understanding on actual pressure. Through comparison of RPV (Reactor Pressure Vessel) and S/C pressures with D/W pressure, such water-column effect was evaluated. Correction for this effect was developed enabling clarification of slight pressure difference among RPV, S/C and D/W. This information was then integrated with other available data such as, water level, CAMS and environmental dose rate, into an interpretation of accident focusing on RPV and PCV pressurization/depressurization and radioactive material release to environment. It is suggested that dryout of in-vessel and ex-vessel debris was likely causing pressure decrease. S/C water poured into pedestal heated by relocated debris was the likely cause of pressurization. Cyclic reflooding of pedestal debris and dryout was likely.

Journal Articles

Large-scale multi-dimensional phenomena found in CCTF and SCTF experiments

Murao, Yoshio; Iguchi, Tadashi; ; Iwamura, Takamichi

Nucl. Eng. Des., 145, p.85 - 95, 1993/00

 Times Cited Count:4 Percentile:45.58(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Modeling of reflooding

G.Yadigaroglu*; R.A.Nelson*; V.Teschendorff*; Murao, Yoshio; J.Kelly*; D.Bestion*

Nucl. Eng. Des., 145, p.1 - 35, 1993/00

 Times Cited Count:23 Percentile:88.24(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Evaluation report on CCTF core-II reflood test C2-15(Run 75); Investigation of FLECHT-SET coupling test results

Okubo, Tsutomu; Iguchi, Tadashi; ; Murao, Yoshio

JAERI-M 91-227, 89 Pages, 1992/01

JAERI-M-91-227.pdf:1.82MB

no abstracts in English

JAEA Reports

Journal Articles

Quenching degradation in-pile experiment on an oxidized fuel rod in the temperature range of 1000 to 1260$$^{circ}$$C

Katanishi, Shoji; Sobajima, Makoto;

Nucl. Eng. Des., 132, p.239 - 251, 1991/00

 Times Cited Count:4 Percentile:48.7(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Accident analyses for a double-flat-core type HCLWR

Okubo, Tsutomu; Iwamura, Takamichi; *; *; Murao, Yoshio

6th Proc. of Nuclear Thermal Hydraulics, p.79 - 86, 1990/11

no abstracts in English

Journal Articles

Accident analyses for a double-flat-core type HCLWR

Okubo, Tsutomu; Iwamura, Takamichi; *; *; Murao, Yoshio

Transactions of the American Nuclear Society, 62, p.662 - 663, 1990/11

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

Evaluation report on SCTF core-III test S3-9; Investigation of CCTF coupling test results under an evaluation model condition in PWRs with cold-leg-injection-type ECCS

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

JAERI-M 90-046, 114 Pages, 1990/03

JAERI-M-90-046.pdf:2.26MB

no abstracts in English

JAEA Reports

Evaluation report on SCTF core-III test S3-17; Investigation of thermo-hydrodynamic behavior during reflood phase of LOCA in a PWR with vent valves

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

JAERI-M 90-036, 120 Pages, 1990/03

JAERI-M-90-036.pdf:2.49MB

no abstracts in English

JAEA Reports

Evaluation report on SCTF core-III tests S3-7 and S3-8; Investigation of tie plate water temperature distribution effects on water break-through and core cooling during reflooding in PWRs with combined-injection-type ECCS

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

JAERI-M 90-035, 143 Pages, 1990/03

JAERI-M-90-035.pdf:3.07MB

no abstracts in English

JAEA Reports

Evaluation report on CCTF core-II reflood test C2-AA2(Run 58); Investigation of downcomer injection effects

Okubo, Tsutomu; Iguchi, Tadashi; Sugimoto, Jun; ; Murao, Yoshio

JAERI-M 89-227, 96 Pages, 1990/01

JAERI-M-89-227.pdf:2.12MB

no abstracts in English

JAEA Reports

Reflood experiments in single rod channel under high-pressure condition

G.Xu*; Kumamaru, Hiroshige; Tasaka, Kanji

JAERI-M 89-178, 35 Pages, 1989/11

JAERI-M-89-178.pdf:0.74MB

no abstracts in English

Journal Articles

Multi-dimensional thermal-hydraulics in pressure vessel during reflood phase of a PWR-LOCA

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

Proc. of the 4th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Vol. 1, p.54 - 59, 1989/10

no abstracts in English

Journal Articles

Two-dimensional fall back flow and core cooling in the slab core test facility: SCTF

; ; ;

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.2 - 129, 1986/00

no abstracts in English

Journal Articles

Experimental modeling of steam-water countercurrent flow limit for perforated plates

Journal of Nuclear Science and Technology, 22(9), p.723 - 732, 1985/00

 Times Cited Count:5 Percentile:60.63(Nuclear Science & Technology)

no abstracts in English

41 (Records 1-20 displayed on this page)