Merge branch '10-correct-energy-deposition-issues' into 'main'

#10: Correct a power normalization issue in module EVO:

See merge request dragon/5.1!18

2 files changed, 3 insertions, 1 deletions

diff --git a/doc/IGE335/Section3.09.tex b/doc/IGE335/Section3.09.tex
index 1c74f3b..a19d348 100644
--- a/doc/IGE335/Section3.09.tex
+++ b/doc/IGE335/Section3.09.tex
@@ -409,7 +409,8 @@ fission for fissile nuclide $i$ is calculated as
 $$E_{{\rm fiss},i}={Q_i \over Q_{\rm 235}} H_{\rm 235}$$
 \noindent where $Q_i$ is the fission pseudo-Q value for fissile nuclide $i$; $Q_{\rm 235}$ is the fission
 pseudo-Q value for U235 and $H_{\rm 235} = 202.27$ MeV is an estimate for the energy deposition per
-fission (including the additional energy released in capture reactions) in a typical light water reactor.
+fission (including the additional energy released in capture reactions) in a typical light water reactor. This option
+assumes that {\tt H-FACTOR} is defined for all heavy isotopes.
 
 \item[\moc{NOGL}] keyword to compute the burnup using the energy released by all isotopes present in
 fuel only. This is the default option.
diff --git a/doc/IGE351/SectDburnup.tex b/doc/IGE351/SectDburnup.tex
index 07cb0d4..76cac21 100644
--- a/doc/IGE351/SectDburnup.tex
+++ b/doc/IGE351/SectDburnup.tex
@@ -63,6 +63,7 @@ $I_{g}=\mathcal{S}^{b}_{10}$ where
 \begin{displaymath}
 I_{g} = \left\{
 \begin{array}{rl}
+ -1 & \textrm{Compute the burnup using the fission rate in $^{235}U$ multiplied by 202.27 MeV} \\
  0 & \textrm{Compute the burnup using the power released in fuel} \\
  1 & \textrm{Compute the burnup using the power released in the global geometry} \\
 \end{array} \right.