Analysis of pressure- and temperature- induced steam generator tube rupture during PWR severe accident initiated from station blackout

Hidaka, Akihide; Maruyama, Yu; Nakamura, Hideo

Proceedings of 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and Safety (NUTHOS-6) (CD-ROM), 15 Pages, 2004/00

Severe accident studies showed that Direct Containment Heating issue was resolved for PWRs because a creep rupture at pressurizer surge line would occur prior to the melt-through of Reactor Pressure Vessel during station blackout (TMLB'). However, it was recently concerned that, if the secondary system is depressurized during TMLB', the creep rupture at SG U-tubes would occur earlier than the surge line. This pressure- and temperature-induced SG U-tube rupture (PTI-SGTR) is not preferable because of the increase in offsite consequences. The SCDAP/RELAP5 analyses by USNRC showed that the surge line would fail earlier than the U-tubes. However, the analyses used a coarse nodilization for steam mixing at the SG inlet plenum that could affect the temperature of U-tubes. To investigate the effect of steam mixing, an analysis was performed with MELCOR1.8.4. The analysis showed that the surge line would fail earliest during TMLB' while the U-tubes could fail earliest during TMLB' with secondary system depressurization. Further investigation is needed for occurrence conditions of PTI-SGTR.

Subcritical to supercritical flow transition in a horizontal stratified flow

; Kukita, Yutaka; *

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 1, 0, p.131 - 136, 1995/00

no abstracts in English

Analysis of reactor piping behavior against thermal loads during severe accident

Hashimoto, Kazuichiro; Nakamura, Naohiko; Igarashi, Minoru*; Maruyama, Yu; Sugimoto, Jun

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering, Vol. 3, 0, p.1241 - 1246, 1995/00

no abstracts in English

Results of 0.5% hot-leg break loss-of-coolant accident experiments at ROSA-IV/LSTF; The effect of break orientation

; Kukita, Yutaka; Yonomoto, Taisuke; *

Nuclear Technology, 96, p.202 - 214, 1991/11

https://doi.org/10.13182/NT91-A34606

no abstracts in English

Flow regime transition in stratified two-phase flow including a hydraulic jump

Katayama, Jiro; Nakamura, Hideo; Kukita, Yutaka

Proc. of the Int. Conf. on Multiphase Flows 91-TSUKUBA,Vol. 1, p.7 - 10, 1991/00

no abstracts in English

Data report for ROSA-IV LSTF 10% hot leg break experiment; Run SB-HL-02

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

JAERI-M 90-039, 122 Pages, 1990/03

JAERI-M-90-039.pdf:3.38MB

no abstracts in English

An Analysis of LOCA Experiment by RELAP-4J; An Analysis of ROSA-II Hot Leg Break Test Run419

JAERI-M 8860, 160 Pages, 1980/05

JAERI-M-8860.pdf:6.24MB

no abstracts in English

ROSA-II Test Data Report,9; The Largest Hot Leg Breaks(Runs 418,419,420,423)

*

JAERI-M 7239, 177 Pages, 1977/09

JAERI-M-7239.pdf:3.93MB

no abstracts in English