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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.
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.
Suzuki, Mitsuhiro; Anoda, Yoshinari
JAERI-Tech 2000-016, p.173 - 0, 2000/03
JAERI-Tech-2000-016.pdf:7.25MB
no abstracts in English
Hidaka, Akihide; Soda, Kunihisa; Sugimoto, Jun
Journal of Nuclear Science and Technology, 32(6), p.527 - 538, 1995/06
Times Cited Count：2 Percentile：28.4(Nuclear Science & Technology)no abstracts in English
Watanabe, Tadashi; Kukita, Yutaka
Proc. of the 6th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics,Vol. 2, p.1232 - 1239, 1993/00
no abstracts in English
Kumamaru, Hiroshige; G.Briday*; Kukita, Yutaka; D.Juhel*; R.Deruaz*
ANS Proc. of the 1992 National Heat Transfer Conf., p.285 - 292, 1992/00
no abstracts in English
A.Annunziato*; C.Addabbo*; G.Briday*; R.Deruaz*; D.Juhel*; Kumamaru, Hiroshige; Kukita, Yutaka; C.Medich*; M.Rigamonti*
Proc. of the 5th Int. Topical Meeting on Reactor Thermal Hydraulics: NURETH-5, p.1570 - 1576, 1992/00
no abstracts in English
Nakamura, Hideo; Anoda, Yoshinari; Kukita, Yutaka
Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.497 - 503, 1991/00
no abstracts in English
