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Study on Pb-Bi-water direct contact boiling two-phase flow and heat transfer

Authors :
Takahashi, M.
Sofue, H.
Iguchi, T.
Pramono, Y.
Huang, F.
Novitrian
Matsumoto, M.
Matsuzawa, T.
Uchida, S.
Source :
Progress in Nuclear Energy. Jul2005, Vol. 47 Issue 1-4, p569-576. 8p.
Publication Year :
2005

Abstract

Abstract: For the development of 45w%Pb-55w%Bi cooled direct contact boiling water small fast reactor (PBWFR), Pb-Bi-water direct contact boiling two-phase flow loop has been fabricated and operated. The loop consists of a Pb-Bi flow loop (four heater pin bundle, a chimney, an upper plenum, a level meter tank, an air-water cooler, and an electromagnetic flow meter) and a water-steam flow loop (a pump, a preheated, an injection nozzle, the chimney, the upper plenum with mist separators and dryers, a condenser, a buffer tank, and an air-water cooler). At the rated operating condition system pressure is 7 MPa. The sub-cooled water was injected into a Pb-Bi flow in the chimney. A power of the heater pin bundle was controlled to obtain the inlet and outlet temperatures of the heater bundle. The Pb-Bi and steam flows were simulated analytically using one-dimensional models of frictional and form losses and a drag force. The Pb-Bi-steam two-phase frictional pressure loss was calculated by means of the two-phase flow multiplication factor of Lockhart-Martinelli model. It was found that Pb-Bi temperature decreased quickly in the chimney due to high heat transfer rate of Pb-Bi-water direct contact boiling. The volumetric overall heat transfer coefficient was 60–310 kW/m3K, and decreased with the superheat. [Copyright &y& Elsevier]

Details

Language :
English
ISSN :
01491970
Volume :
47
Issue :
1-4
Database :
Academic Search Index
Journal :
Progress in Nuclear Energy
Publication Type :
Academic Journal
Accession number :
19184655
Full Text :
https://doi.org/10.1016/j.pnucene.2005.05.059