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save event nuclide rather than event element so that it is compatible with nuclide tally filters

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This commit is contained in:
liangjg 2019-04-10 16:43:25 -04:00
parent e7ab0b704c
commit a795de2db5
2 changed files with 14 additions and 9 deletions
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2
include/openmc/physics.h
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@ -44,7 +44,7 @@ void sample_positron_reaction(Particle* p);
//!
//! \param[in] p Particle
//! \return Index in the data::nuclides vector
int sample_nuclide(const Particle* p);
int sample_nuclide(Particle* p);
//! Determine the average total, prompt, and delayed neutrons produced from
//! fission and creates appropriate bank sites.

21
src/physics.cpp
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@ -68,7 +68,7 @@ void collision(Particle* p)
data::nuclides[p->event_nuclide_]->name_ << ". Energy = " << p->E_ << " eV.";
} else if (p->type_ == Particle::Type::photon) {
msg << " " << reaction_name(p->event_mt_) << " with " <<
data::elements[p->event_nuclide_].name_ << ". Energy = " << p->E_ << " eV.";
data::nuclides[p->event_nuclide_]->name_ << ". Energy = " << p->E_ << " eV.";
} else {
msg << " Disappeared. Energy = " << p->E_ << " eV.";
}
@ -81,9 +81,6 @@ void sample_neutron_reaction(Particle* p)
// Sample a nuclide within the material
int i_nuclide = sample_nuclide(p);
// Save which nuclide particle had collision with
p->event_nuclide_ = i_nuclide;
// Create fission bank sites. Note that while a fission reaction is sampled,
// it never actually "happens", i.e. the weight of the particle does not
// change when sampling fission sites. The following block handles all
@ -213,7 +210,6 @@ void sample_photon_reaction(Particle* p)
// Sample element within material
int i_element = sample_element(p);
p->event_nuclide_ = i_element;
const auto& micro {p->photon_xs_[i_element]};
const auto& element {data::elements[i_element]};
@ -398,7 +394,7 @@ void sample_positron_reaction(Particle* p)
p->event_ = EVENT_ABSORB;
}
int sample_nuclide(const Particle* p)
int sample_nuclide(Particle* p)
{
// Sample cumulative distribution function
double cutoff = prn() * p->macro_xs_.total;
@ -415,7 +411,11 @@ int sample_nuclide(const Particle* p)
// Increment probability to compare to cutoff
prob += atom_density * p->neutron_xs_[i_nuclide].total;
if (prob >= cutoff) return i_nuclide;
if (prob >= cutoff) {
// Save which nuclide particle had collision with
p->event_nuclide_ = i_nuclide;
return i_nuclide;
}
}
// If we reach here, no nuclide was sampled
@ -442,7 +442,12 @@ int sample_element(Particle* p)
// Increment probability to compare to cutoff
prob += sigma;
if (prob > cutoff) return i_element;
if (prob > cutoff) {
// Save which nuclide particle had collision with
p->event_nuclide_ = mat->nuclide_[i];
return i_element;
}
}
// If we made it here, no element was sampled