From 0f2863b488433a8492f27aa7cd9b78ace2d8faba Mon Sep 17 00:00:00 2001
From: Andrew Johnson <ajohnson400@gatech.edu>
Date: Fri, 24 Jan 2020 10:42:55 -0500
Subject: [PATCH] Allow control over status messages in Chain.from_endf

---
 openmc/deplete/chain.py | 21 ++++++++++++++++-----
 1 file changed, 16 insertions(+), 5 deletions(-)

diff --git a/openmc/deplete/chain.py b/openmc/deplete/chain.py
index 662106a696..608d45a437 100644
--- a/openmc/deplete/chain.py
+++ b/openmc/deplete/chain.py
@@ -189,7 +189,7 @@ class Chain(object):
         return len(self.nuclides)
 
     @classmethod
-    def from_endf(cls, decay_files, fpy_files, neutron_files):
+    def from_endf(cls, decay_files, fpy_files, neutron_files, progress=True):
         """Create a depletion chain from ENDF files.
 
         Parameters
@@ -200,12 +200,20 @@ class Chain(object):
             List of ENDF neutron-induced fission product yield sub-library files
         neutron_files : list of str
             List of ENDF neutron reaction sub-library files
+        progress : bool, optional
+            Flag to print status messages during processing. Does not
+            effect warning messages
+
+        Returns
+        -------
+        Chain
 
         """
         chain = cls()
 
         # Create dictionary mapping target to filename
-        print('Processing neutron sub-library files...')
+        if progress:
+            print('Processing neutron sub-library files...')
         reactions = {}
         for f in neutron_files:
             evaluation = openmc.data.endf.Evaluation(f)
@@ -219,7 +227,8 @@ class Chain(object):
                     reactions[name][mt] = q_value
 
         # Determine what decay and FPY nuclides are available
-        print('Processing decay sub-library files...')
+        if progress:
+            print('Processing decay sub-library files...')
         decay_data = {}
         for f in decay_files:
             data = openmc.data.Decay(f)
@@ -228,13 +237,15 @@ class Chain(object):
                 continue
             decay_data[data.nuclide['name']] = data
 
-        print('Processing fission product yield sub-library files...')
+        if progress:
+            print('Processing fission product yield sub-library files...')
         fpy_data = {}
         for f in fpy_files:
             data = openmc.data.FissionProductYields(f)
             fpy_data[data.nuclide['name']] = data
 
-        print('Creating depletion_chain...')
+        if progress:
+            print('Creating depletion_chain...')
         missing_daughter = []
         missing_rx_product = []
         missing_fpy = []