09.06.2013 Views

KURENAI : Kyoto University Research Information Repository

KURENAI : Kyoto University Research Information Repository

KURENAI : Kyoto University Research Information Repository

SHOW MORE
SHOW LESS

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

On the other hand, in a later stage of the LOCA and reflooding where<br />

liquid flow rate is extremely low, the pool entrainment phenomena play im-<br />

portant roles in heat and mass transfer processes. Therefore, these phenomena<br />

were studied. Droplets which are suspended from a free surface are<br />

partly carried away by streaming gas and partly returned back to the free<br />

surface by gravity. A correlation is developed for the pool<br />

entrainment amount based on simple mechanistic modeling and a number of<br />

data. This analysis reveals that there exist three regions of entrainment<br />

in the axial direction from a pool surface. .In the first region (near<br />

surface region), entrainment is independent of height and gas velocity.<br />

In the second region (momentum controlled region), the amount of<br />

entrainment decreases with increasing height from the free surface and<br />

increases with increasing gas velocity. . In the third region (deposition<br />

controlled region), the entrainment increases with increasing gas velocity<br />

and decreases with increasing height due to deposition of droplets. The<br />

present correlation agrees well with a large number of experimental data<br />

over a wide range of pressure for air-water and steam-water systems.<br />

Along with the separate effects of the transient boiling and two-phase<br />

flow on the thermohydraulic characteristics of a nuclear reactor, the over-<br />

rall characteristics throughout the entire loop of a nuclear reactor com-<br />

prise another set of important problems. The phenomena correspond to the<br />

transient boiling and two-phase flow under extremely large t/dh e where t<br />

covers the entire loop. One of the most important applications of the<br />

above problems is the natural circulation coolability. The phenomena are<br />

particularly important associated with small break LOCA and subsequent pump<br />

trip in a nuclear reactor. A model facility is often used in evaluating<br />

the natural circulation coolability. In designing the model facility.<br />

which' simulates a prototype reactor, , scaling laws are impotant. Therefore,<br />

scaling criteria for a natural circulation loop under single phase and<br />

two-phase flow conditions have been derived. For a single phase case the<br />

continuity, integral momentum, and energy equations in one-dimensional area<br />

average forms have been used. From this, the geometrical similarity groups,<br />

friction number, Richardson number, characteristic time constant ratio, Biot<br />

number, and heat source number are obtained. The Biot number involves the<br />

heat transfer coefficient which may cause some difficulties in simulating the<br />

373

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!