From 58e39c9ff0c179589cd6c02cd4301ec7a2a576fa Mon Sep 17 00:00:00 2001
From: Morfouace <pierre.morfouace@gmail.com>
Date: Wed, 13 May 2020 11:53:49 +0200
Subject: [PATCH] Writting neutron induced fission cross section in
MaterialManager
---
NPSimulation/Core/MaterialManager.cc | 10 +++++++++-
Projects/PISTA/PISTA.detector | 2 +-
Projects/Scone/Analysis.cxx | 9 +++++----
3 files changed, 15 insertions(+), 6 deletions(-)
diff --git a/NPSimulation/Core/MaterialManager.cc b/NPSimulation/Core/MaterialManager.cc
index 5ad7f3859..a4fe23398 100644
--- a/NPSimulation/Core/MaterialManager.cc
+++ b/NPSimulation/Core/MaterialManager.cc
@@ -1192,6 +1192,7 @@ void MaterialManager::WriteCrossSectionTable(G4ParticleDefinition* Particle, G4d
G4String path1;
G4String path2;
G4String path3;
+ G4String path4;
G4String ParticleName = Particle->GetParticleName();
G4String MaterialName = it->second->GetName();
G4String ElementName = it->second->GetElement(i)->GetName();
@@ -1199,13 +1200,16 @@ void MaterialManager::WriteCrossSectionTable(G4ParticleDefinition* Particle, G4d
path1 = GlobalPath + "/Inputs/CrossSection/" + "G4XS_elastic_" + ParticleName + "_" + ElementName + ".dat";
path2 = GlobalPath + "/Inputs/CrossSection/" + "G4XS_inelastic_" + ParticleName + "_" + ElementName + ".dat";
path3 = GlobalPath + "/Inputs/CrossSection/" + "G4XS_capture_" + ParticleName + "_" + ElementName + ".dat";
+ path4 = GlobalPath + "/Inputs/CrossSection/" + "G4XS_fission_" + ParticleName + "_" + ElementName + ".dat";
ofstream ofile_elastic;
ofstream ofile_inelastic;
ofstream ofile_capture;
+ ofstream ofile_fission;
ofile_elastic.open(path1);
ofile_inelastic.open(path2);
ofile_capture.open(path3);
+ ofile_fission.open(path4);
//std::cout << path << std::endl;
double xs;
double step_keV = 1*keV;
@@ -1230,12 +1234,16 @@ void MaterialManager::WriteCrossSectionTable(G4ParticleDefinition* Particle, G4d
// Capture Cross Section
xs = store->GetCaptureCrossSectionPerAtom(Particle, E, it->second->GetElement(i), it->second);
ofile_capture << E/MeV << " " << xs/barn << G4endl;
-
+
+ // Fission Cross Section
+ xs = store->GetFissionCrossSectionPerAtom(Particle, E, it->second->GetElement(i), it->second);
+ ofile_fission << E/MeV << " " << xs/barn << G4endl;
}
ofile_elastic.close();
ofile_inelastic.close();
ofile_capture.close();
+ ofile_fission.close();
}
}
}
diff --git a/Projects/PISTA/PISTA.detector b/Projects/PISTA/PISTA.detector
index a9f6077ef..bc33042c2 100644
--- a/Projects/PISTA/PISTA.detector
+++ b/Projects/PISTA/PISTA.detector
@@ -1,6 +1,6 @@
%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
Target
- THICKNESS= 0.44 micrometer
+ THICKNESS= 0.22 micrometer
RADIUS= 20 mm
MATERIAL= C
ANGLE= 0 deg
diff --git a/Projects/Scone/Analysis.cxx b/Projects/Scone/Analysis.cxx
index 01bb49a29..c7210aba9 100644
--- a/Projects/Scone/Analysis.cxx
+++ b/Projects/Scone/Analysis.cxx
@@ -84,9 +84,9 @@ void Analysis::TreatEvent(){
E_sum += Scone->Energy[i];
}
}
-
+ E_sum = E_sum - E_init;
//if(Time_max>50) m_DetectedNeutron++;
- if(Time_max>40 && E_sum>2) m_DetectedNeutron++;
+ if(Time_max>50 && E_sum>0) m_DetectedNeutron++;
}
////////////////////////////////////////////////////////////////////////////////
@@ -125,11 +125,12 @@ void Analysis::End(){
cout << "DetectedNeutron: " << endl;
ofstream ofile;
- ofile.open("macro/eff_scone_natGd25um_Esum2MeV.txt");
+ ofile.open("macro/eff_scone_natGd25um.txt");
//ofile.open("macro/eff_scone_menate.txt");
for(int i=0; i< vDetectedNeutron.size(); i++){
+ //cout << "* " << vE_init[i] << " / " << vDetectedNeutron[i]/vDetectedNeutron[0]*99.4 << endl;
cout << "* " << vE_init[i] << " / " << vDetectedNeutron[i]/1e5*100 << endl;
- //ofile << vE_init[i] << " " << vDetectedNeutron[i]/vDetectedNeutron[0]*99.3 << endl;
+ //ofile << vE_init[i] << " " << vDetectedNeutron[i]/vDetectedNeutron[0]*99.4 << endl;
ofile << vE_init[i] << " " << vDetectedNeutron[i]/1e5*100 << endl;
}
ofile.close();
--
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