2017 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 306-1 Nuclear Safety Engineering, Nuclear Installation Safety, PSA

[2M01-06] LWR performance duirng an accident

Tue. Mar 28, 2017 9:35 AM - 11:10 AM Room M (16-504 Building No.16)

Chair: Hidemasa Yamano (JAEA)

10:05 AM - 10:20 AM

[2M03] Thermal-dydraulic Analysis of BWR Containment Response to Accidents Using the GOTHIC Therrmal Hydraulic Analysis Package

(2)Loss of pressure suppression capability in S/P

*Hiroshi Kawai1, Tatsuya Hayasaki1, Daisuke Fujiwara1 (1. TEPCO SYSTEMS CORPORATION)

Keywords:GOTHIC, MAAP, S/P condensation capability, SRV tail pipe break, Primary containment

Performed evaluation of the steam condensation behavior at the surface of S/P and containment pressure behavior including pressure suppression capability by the steam condensation in case of a SRV tail pipe break in the air space of S/C with multi-dimensional analysis using GOTHIC code.