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JAEA Reports

Data report of ROSA/LSTF experiment SB-SL-01; Main steam line break accident

Takeda, Takeshi

JAEA-Data/Code 2020-019, 58 Pages, 2021/01

JAEA-Data-Code-2020-019.pdf:3.85MB

An experiment denoted as SB-SL-01 was conducted on March 27, 1990 using the Large Scale Test Facility (LSTF) in the Rig of Safety Assessment-IV (ROSA-IV) Program. The ROSA/LSTF experiment SB-SL-01 simulated a main steam line break (MSLB) accident in a pressurized water reactor (PWR). The test assumptions were made such as auxiliary feedwater (AFW) injection into secondary-side of both steam generators (SGs) and coolant injection from high pressure injection (HPI) system of emergency core cooling system into cold legs in both loops. The MSLB led to a fast depressurization of broken SG, which caused a decrease in the broken SG secondary-side wide-range liquid level. The broken SG secondary-side wide-range liquid level recovered because of the AFW injection into the broken SG secondary-side. The primary pressure temporarily decreased a little just after the MSLB, and increased up to 16.1 MPa following the closure of the SG main steam isolation valves. Coolant was manually injected from the HPI system into cold legs in both loops a few minutes after the primary pressure reduced to below 10 MPa. The primary pressure raised due to the HPI coolant injection, but was kept at less than 16.2 MPa by fully opening a power-operated relief valve of pressurizer. The core was filled with subcooled liquid through the experiment. Thermal stratification was seen in intact loop cold leg during the HPI coolant injection owing to the flow stagnation. On the other hand, significant natural circulation prevailed in broken loop. When the continuous core cooling was ensured by the successive coolant injection from the HPI system, the experiment was terminated. The experimental data obtained would be useful to consider recovery actions and procedures in the multiple fault accident with the MSLB of PWR. This report summarizes the test procedures, conditions, and major observations in the ROSA/LSTF experiment SB-SL-01.

Journal Articles

RELAP5 uncertainty evaluation using ROSA/LSTF test data on PWR 17% cold leg intermediate-break LOCA with single-failure ECCS

Takeda, Takeshi; Otsu, Iwao

Annals of Nuclear Energy, 109, p.9 - 21, 2017/11

 Times Cited Count:8 Percentile:60.93(Nuclear Science & Technology)

JAEA Reports

ROSA/LSTF experiment report for RUN SB-CL-24; Repeated core heatup phenomena during 0.5% cold leg break

Suzuki, Mitsuhiro; Anoda, Yoshinari

JAERI-Tech 2000-016, p.173 - 0, 2000/03

JAERI-Tech-2000-016.pdf:7.25MB

no abstracts in English

Journal Articles

Secondary-side depressurization during PWR cold-leg small break LOCAs based on ROSA-V/LSTF experiments and analyses

Asaka, Hideaki; Anoda, Yoshinari; Kukita, Yutaka*;

Journal of Nuclear Science and Technology, 35(12), p.905 - 915, 1998/12

 Times Cited Count:15 Percentile:74.74(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Data report for ROSA-IV LSTF 5% cold leg break LOCA experiment Run SB-CL-08

Kukita, Yutaka; *; *; Anoda, Yoshinari; Kumamaru, Hiroshige; Suzuki, Mitsuhiro; ; Yamamoto, Nobuo; Nakamura, Hideo; Yonomoto, Taisuke; et al.

JAERI-M 89-220, 127 Pages, 1990/01

JAERI-M-89-220.pdf:3.57MB

no abstracts in English

Journal Articles

Results of 0.5% cold-leg small-break LOCA experiments at ROSA-IV/LSTF; Effect of break orientation

; Kukita, Yutaka; Yonomoto, Taisuke; Koizumi, Yasuo; Tasaka, Kanji

Experimental Thermal and Fluid Science, 3, p.588 - 596, 1990/00

 Times Cited Count:18 Percentile:76.54(Thermodynamics)

no abstracts in English

Journal Articles

Results of 0.5 % cold leg break LOCA experiments at ROSA-IV/LSTF; Effect of break orientation

; Tasaka, Kanji; *; Kukita, Yutaka; Yonomoto, Taisuke

Proc. of the 4th Int. Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Vol. 1, p.206 - 213, 1989/10

no abstracts in English

Journal Articles

Assessment of current safety evaluation analysis on reflood behavior during PWR-LOCA by using CCTF data

; Murao, Yoshio; ; ; ; *

Journal of Nuclear Science and Technology, 24(11), p.887 - 896, 1987/11

 Times Cited Count:2 Percentile:29.75(Nuclear Science & Technology)

no abstracts in English

Journal Articles

On the recent accomplishments of LOFT program

;

Nihon Genshiryoku Gakkai-Shi, 21(8), p.613 - 624, 1979/00

 Times Cited Count:0

no abstracts in English

JAEA Reports

ROSA-II Test Date Report,6

*; ; ; ; ;

JAERI-M 6849, 142 Pages, 1976/12

JAERI-M-6849.pdf:3.24MB

no abstracts in English

JAEA Reports

ROSA-II Test Data Report,No.5; Runs 310,311,312,313,317

; *; *; ; ; ; ; ; ; ; et al.

JAERI-M 6709, 169 Pages, 1976/09

JAERI-M-6709.pdf:3.82MB

no abstracts in English

JAEA Reports

An Experimental Study on Performance of Upper Head Injection System by the ROSA-II

; ; *; *; ; *; ; ; ; ; et al.

JAERI-M 6707, 169 Pages, 1976/09

JAERI-M-6707.pdf:4.2MB

no abstracts in English

15 (Records 1-15 displayed on this page)
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