Experimental study on secondary depressurization action for PWR vessel bottom small break LOCA with HPI failure and gas inflow (ROSA-V/LSTF test SB-PV-03)

Suzuki, Mitsuhiro; Takeda, Takeshi; Asaka, Hideaki; Nakamura, Hideo

JAERI-Research 2005-014, 170 Pages, 2005/06

JAERI-Research-2005-014.pdf:7.64MB

A small break LOCA (SBLOCA) experiment was conducted at the LSTF of ROSA-V program to study effects of accident management (AM) on core cooling, which is important in case of high pressure injection (HPI) system failure during an SBLOCA at a PWR. The experiment, SB-PV-03, simulated ten instrument-tube break LOCA at the PWR vessel bottom equivalent to 0.2% cold leg break, total HPI failure, non-condensable gas inflow from accumulator injection system (AIS) and AM actions on secondary depressurization at -55 K/h and auxiliary feedwater (AFW) supply for 30 minutes. It was clarified that the AM actions were effective on primary depressurization until AIS injection end at 1.6 MPa, but thereafter became less effective by the gas inflow, resulting in low pressure injection (LPI) delay and whole core heatup under continuous water discharge at the break. The report describes these phenomena including core heatup related with primary coolant mass and AM actions, primary-to-secondary heat transfer analysis and estimation of gas in the primary loops.

Safety analyses of a passive safety light water reactor JPSR

Araya, Fumimasa; Iwamura, Takamichi; Yoshida, Hiroyuki; Kunii, Katsuhiko; Okumura, Keisuke; Murao, Yoshio

10th Pacific Basin Nuclear Conf. (10-PBNC), 1, p.299 - 305, 1996/00

no abstracts in English

Application of new coolant inventory tracking method to PWR small break LOCA simulation experiments at ROSA-IV/LSTF

Suzuki, Mitsuhiro

Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering, p.311 - 317, 1991/00

no abstracts in English

Core liquid level depression due to manometric effect during PWR small break LOCA; Effect of core bypass

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

Journal of Nuclear Science and Technology, 25(3), p.274 - 282, 1988/00

https://doi.org/10.3327/jnst.25.274

no abstracts in English

Slug to annular flow transition during boiloff in a rod bundle under high-pressure conditions

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

Nucl.Eng.Des., 98, p.69 - 76, 1986/00

https://doi.org/10.1016/0029-5493(86)90121-4

no abstracts in English