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.

Analysis of steam generator tube rupture as a severe accident using MELCOR1.8.4

H.Yang*; Hidaka, Akihide; Sugimoto, Jun

JAERI-Tech 99-013, 97 Pages, 1999/03

JAERI-Tech-99-013.pdf:3.24MB

no abstracts in English

Accident sequence precursor analyses for steam generator tube rupture events that actually occurred

Watanabe, Norio

Reliab. Eng. Syst. Saf., 57, p.281 - 297, 1997/00

https://doi.org/10.1016/S0951-8320(97)00047-1

no abstracts in English

Break flow modeling for a steam generator tube rupture(SGTR) incident in a pressurized water reactor(PWR)

*; Watanabe, Tadashi; Kukita, Yutaka

JAERI-M 93-236, 34 Pages, 1993/12

JAERI-M-93-236.pdf:0.95MB

no abstracts in English

Analysis of ROSA-IV/LSTF experiment simulating a steam generator tube rupture design basis incident by using RELAP5/MOD2 code

Watanabe, Tadashi; M.Wang*; Kukita, Yutaka

JAERI-M 93-039, 26 Pages, 1993/03

JAERI-M-93-039.pdf:0.85MB

no abstracts in English

Trend analysis for incidents of steam generator tube rupture and loss of electric power based on IRS reports

Fujiki, Kazuo; Ishigami, Tsutomu;

Proc. OECD/CSNI-CEC Specialist Meeting Trend and Pattern Analyses of Operational Data from NPP, p.407 - 418, 1990/00

no abstracts in English

A Simulation of steam generator tube rupture accident by safety analysis code RELAP5/Mod1

*; *; *; Fujiki, Kazuo; Kosaka, Atsuo; *

Tech. Rep. Inst. At. Energy,Kyoto Univ., 211, p.1 - 57, 1989/05

no abstracts in English