Published October 2000 | Version v1
Book

Single U-tube testing and RELAP5 code analysis of PCCS with horizontal heat exchanger

  • 1. Dept. of Reactor Safety Research, Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
  • 2. Research and Development Dept., Japan Atomic Power Co., Tokyo (Japan)

Description

A passive containment cooling sy stem (PCCS) is under planning to use in a next-generation-type BWR for long-term cooling by condensing steam in heat exchangers especially during a severe accident when a containment spray system is in failure. JAER1 and JAPC started a cooperative study to verify the performance of the PCCS using horizontal heat exchange in 1998. Fundamental heat exchanger performance was studied using a horizontal single U-tube test facility under postulated severe accident conditions. Studied phenomena included condensation heat transferin horizontal tube (19, 32 and 43 mm o.d., 8 m long) being degraded by non-condensable gas up to total pressure of 0.7 MPa, pressure loss and discharge behavior of condensate and non-condensable gas. Steam was totally condensed with a small pressure drop across the condenser tube. Condensation degradation was insignificant even at high gas concentration, suggesting that horizontal U-tube heat exchanger is promising for the PCCS purpose. The experimental results were used for verification of RELAP5/MOD3 code in post test calculations. The RELAP5 code was modified by incorporating correlations based on the test results, as the original code underpredicted the data. The modified code predicted the data well under both the pure steam and steam-gas mixture inlet conditions. (author)

Part of:
Proceedings of NTHAS2: Second Japan-Korea symposium on nuclear thermal hydraulics and safety

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
Proceedings of NTHAS2: Second Japan-Korea symposium on nuclear thermal hydraulics and safety
Imprint Pagination
800 p.
Journal Page Range
p. 336-343

Conference

Title
2. Japan-Korea symposium on nuclear thermal hydraulics and safety
Acronym
NTHAS2
Dates
15-18 Oct 2000
Place
Fukuoka (Japan)

Optional Information

Notes
1 tab., 10 figs., 22 refs.