Refine your search:     
Report No.
 - 
Search Results: Records 1-12 displayed on this page of 12
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Data report of ROSA/LSTF experiment SB-HL-12; 1% Hot leg break LOCA with SG depressurization and gas inflow

Takeda, Takeshi

JAEA-Data/Code 2015-022, 58 Pages, 2016/01

JAEA-Data-Code-2015-022.pdf:3.31MB

The SB-HL-12 test simulated PWR 1% hot leg SBLOCA under assumptions of total failure of HPI system and non-condensable gas (nitrogen gas) inflow. SG depressurization by fully opening relief valves in both SGs as AM action was initiated immediately after maximum fuel rod surface temperature reached 600 K. After AM action due to first core uncovery by core boil-off, the primary pressure decreased, causing core mixture level swell. The fuel rod surface temperature then increased up to 635 K. Second core uncovery by core boil-off took place before LSC induced by steam condensation on ACC coolant injected into cold legs. The core liquid level recovered rapidly after LSC. The fuel rod surface temperature then increased up to 696 K. The pressure difference became larger between the primary and SG secondary sides after nitrogen gas inflow. Third core uncovery by core boil-off occurred during reflux condensation. The maximum fuel rod surface temperature exceeded 908 K.

JAEA Reports

Data report of ROSA/LSTF experiment SB-CL-32; 1% cold leg break LOCA with SG depressurization and no gas inflow

Takeda, Takeshi

JAEA-Data/Code 2014-021, 59 Pages, 2014/11

JAEA-Data-Code-2014-021.pdf:5.16MB

Experiment SB-CL-32 was conducted on May 28, 1996 using the LSTF. The experiment SB-CL-32 simulated 1% cold leg small-break LOCA in PWR under assumptions of total failure of HPI system and no inflow of non-condensable gas from ACC tanks. Secondary-side depressurization of both SGs as AM action to achieve the depressurization rate of 200 K/h in the primary system was initiated 10 min after break. Core uncovery started with liquid level drop in crossover leg downflow-side. The core liquid level recovered rapidly after first LSC. The surface temperature of simulated fuel rod then increased up to 669 K. Core uncovery took place before second LSC induced by steam condensation on ACC coolant. The core liquid level recovered rapidly after second LSC. The maximum fuel rod surface temperature was 772 K. The continuous core cooling was confirmed because of coolant injection by LPI system. This report summarizes the test procedures, conditions and major observation.

Journal Articles

Non-condensable gas effects in ROSA/AP600 small-break LOCA experiments

Nakamura, Hideo; Kukita, Yutaka; R.A.Shaw*; R.R.Schultz*

Proc. of ASME$$cdot$$JSME 4th Int. Conf. on Nuclear Engineering 1996 (ICONE-4), 1(PART A), p.237 - 244, 1996/00

no abstracts in English

Journal Articles

PWR thermal-hydraulic phenomena following loss of residual heat removal(RHR) during mid-loop operation

Nakamura, Hideo; Kukita, Yutaka

Int. Conf. on New Trends in Nulear System Thermohydraulics,Vol. 1, 0, p.77 - 86, 1994/00

no abstracts in English

Journal Articles

CCFL characteristics of PWR steam generator U-tubes

Yonomoto, Taisuke; Anoda, Yoshinari; Kukita, Yutaka; Y.Peng*

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.522 - 529, 1991/00

no abstracts in English

Journal Articles

Effect of steam generator secondary inventory on reflux condensation

; Koizumi, Yasuo; Osakabe, Masahiro; ; Tasaka, Kanji

86-WA/NE-8, p.1 - 6, 1986/00

no abstracts in English

Journal Articles

The Noncondensable gas effects on loss-of-coolant accident steam condensation loads in BWR pressure suppression pool

; ; ;

Nuclear Technology, 63, p.337 - 346, 1983/00

 Times Cited Count:9 Percentile:30.76(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Method of estimating liquid velocity in a hot leg during reflux cooling of natural circulation in a pressurized water reactor

Soda, Kunihisa

Journal of Nuclear Science and Technology, 19(10), p.813 - 820, 1982/00

 Times Cited Count:4 Percentile:51.49(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Post-facta analysis of the TMI accident, I; Analysis of thermal hydraulic behavior by use of the RELAP4/MOD6/U4/J2

; ; ; Shimooke, Takanori

Nucl.Eng.Des., 69(1), p.3 - 36, 1982/00

 Times Cited Count:2 Percentile:66.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

12 (Records 1-12 displayed on this page)
  • 1