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Next: Flow boiling in a Up: Core flow modeling Previous: Core flow modeling   Contents   Index Introduction
In this chapter we present the model of the flow, ie the hydraulics, of the
core.
The flow in a BWR-core is complicated by a number of special phenomena of which
some are not encountered in boiling two-phase flows elsewhere.
The first complication is that the flow is distributed between an active flow
which flows through the fuel assemblies and a so-called bypass flow which
flows in the cross section between the fuel assemblies ([18, p.
280] and [41, p. 2-16]). Typically the bypass flow
amounts to approximately 10 percent of the total core flow, ie it represents a
non-negligible part of the core flow. We will, however, due to time constraints
be forced to neglect the bypass flow, ie assume all flow through the core to
pass through the fuel assemblies.
The next phenomenon which requires special attention is the influence of the
grid spacers. The approximately seven grid spacers serve as mechanical
stabilizers which ensure that the bow of the fuel pins is kept at a minimum and
fluid-mechanical oscillations are prevented. The spacers disturb the flow field
in a complicated way--they enhance transverse mixing and perhaps most importantly
induce a pressure loss of considerable size.
A special phenomenon which occurs in a nuclear reactor is that some of the heat
(approximately 3 percent [11]) is added in a volumetric manner by
absorption of energy associated with nuclear radiation (both n- and
The flow model to be utilized is based on a so-called mixture formulation of the time and cross-section averaged conservation equations. Before discussing the flow model we have to introduce some general description notation and quantities relevant to boiling two-phase flow.
Next: Flow boiling in a Up: Core flow modeling Previous: Core flow modeling   Contents   Index Revision 2.0, Copyright © 1999-2004 Jakob Christensen http://www.JakobCHR.com E-Mail: webmaster@JakobCHR.com
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