Published 2009 | Version v1
Miscellaneous

Steam-water pressure drop under high pressure condition

  • 1. Japan Atomic Energy Agency, Tokai, Ibaraki (Japan)

Description

For the Steam Generator (SG) in a commercialized sodium cooled Faster Breeder Reactor, flow instability in water side is one of the most important items need researching. As the first step of the research, thermal hydraulics experiments using water as test fluid were performed under high pressure condition at JAEA with using a circular tube. Pressure drop, heat transfer coefficients and void fraction data were derived. This paper focuses on the discussion to steam-water pressure drop. We evaluated existing correlations for two-phase flow multiplier under high pressure. As a result, Chismholm correlation was confirmed being the best one for the present high pressure data. (author)

Part of:
NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics

Additional details

Publishing Information

Imprint Title
NURETH-13: Proceedings of the 13th international topical meeting on nuclear reactor thermal hydraulics
Imprint Pagination
[4617 p.]
Journal Page Range
[10 p.]

Conference

Title
13. international topical meeting on nuclear reactor thermal hydraulics
Acronym
NURETH-13
Dates
27 Sep - 2 Oct 2009
Place
Kanazawa, Ishikawa (Japan)

Optional Information

Notes
Available as CD-ROM Data in PDF format, Folder Name: FullPaper, Paper ID: N13P1188.pdf