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Next: Choosing a grid Neutronics Up: Calculating the power distribution Previous: Calculating Efiss   Contents   Index Local scale power distribution
When we want to calculate the thermal-hydraulics behavior of the reactor core we
have to consider not only the large scale power distribution but also the more
local distribution of power among fuel, moderator and structural materials
present in the core.
We will, however, not go into a detailed discussion of this subject. We assume that
a fraction, Rf, of the total energy release occurs in fuel and the rest,
1-Rf, is released in the moderator. A mathematical definition of Rf is
where qk,fuel' and qk' are the linear heat generation rate in fuel and the total linear heat generation rate respectively measured in [W/m]. According to [11, p. 158], we are safe to assume that more than 97 per cent of the energy release occurs in the fuel [11, p.158]. This is supported by figures [12, p. 21] of the power distribution in a reactor design similar to that of the Swedish Oscarshamn reactor. In this case 97.1 percent of the energy is generated within the fuel.
The part of the power which is generated within the fuel is conducted and
convected to the coolant through the fuel rods by means of a heat flux,
q''. The heat flux at node k, qk'', is determined by
where PH is the heated perimeter in
where
An energy conservation for the vapor-liquid mixture states that
where Ac is the cross-sectional flow area in [
Using (1.111) we can write
where
The magnitude of qg,k''' is usually much smaller than
W for water at saturation is depicted in Figure 1.4 for three different pressures.
Next: Choosing a grid Neutronics Up: Calculating the power distribution Previous: Calculating Efiss   Contents   Index Revision 2.0, Copyright © 1999-2004 Jakob Christensen http://www.JakobCHR.com E-Mail: webmaster@JakobCHR.com
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