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Next: Local scale power distribution Up: Calculating the power distribution Previous: Calculating the power distribution   Contents   Index

Calculating Efiss

The majority of thermal nuclear power reactors use slightly enriched $\mbox{UO}_2$ fuel. In these fuels fission may occur not only in 235U but also in 238U by fast neutrons. This necessitates a discussion of the choice of Efiss in (1.102). According to [11, p. 159], fission of 238U may account for as much as 20 percent of the total number of fissions and since the energy release for fission of 238U is about 3 percent higher compared to fission in 235U (see Table 1.1, p. [*]) we are able to make the following worst case calculation


\begin{eqnarray*}
E_{fiss,exact} &=& 0.8 E_{fiss,\mbox{${}^{235}$U}} + 0.2 E_{f...
...mbox{${}^{235}$U}})
\approx 1.006 E_{fiss,\mbox{${}^{235}$U}}
\end{eqnarray*}


$\textstyle \parbox{1.50cm}{\begin{eqnarray}
\end{eqnarray}}$

Accordingly, if we assume Efiss to be that of 235U a negligible error in the order of only a half percent is introduced. In all practical calculations that follow we make this approximation.

 
 

 
 
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