mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 22:26:08 -04:00
Random Ray Adjoint Mode (#3191)
Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
This commit is contained in:
John Tramm
GitHub
parent
fbb115921c
commit
172867b1df
21 changed files with 958 additions and 169 deletions
|
|
@ -542,7 +542,7 @@ in that cell for the iteration from Equation :eq:`phi_naive` to:
|
|||
.. math::
|
||||
:label: phi_missed_one
|
||||
|
||||
\phi_{i,g,n}^{missed} = \frac{Q_{i,g,n} }{\Sigma_{t,i,g}}
|
||||
\phi_{i,g,n}^{missed} = \frac{Q_{i,g,n} }{\Sigma_{t,i,g}}
|
||||
|
||||
as the streaming operator has gone to zero. While this is obviously innacurate
|
||||
as it ignores transport, for most problems where the region is only occasionally
|
||||
|
|
@ -1060,6 +1060,49 @@ random ray and Monte Carlo, however.
|
|||
develop the scattering source by way of inactive batches before beginning
|
||||
active batches.
|
||||
|
||||
------------------------
|
||||
Adjoint Flux Solver Mode
|
||||
------------------------
|
||||
|
||||
The random ray solver in OpenMC can also be used to solve for the adjoint flux,
|
||||
:math:`\psi^{\dagger}`. In combination with the regular (forward) flux solution,
|
||||
the adjoint flux is useful for perturbation methods as well as for computing
|
||||
weight windows for subsequent Monte Carlo simulations. The adjoint flux can be
|
||||
thought of as the "backwards" flux, representing the flux where a particle is
|
||||
born at an absoprtion point (and typical absorption energy), and then undergoes
|
||||
transport with a transposed scattering matrix. That is, instead of sampling a
|
||||
particle and seeing where it might go as in a standard forward solve, we will
|
||||
sample an absorption location and see where the particle that was absorbed there
|
||||
might have come from. Notably, for typical neutron absorption at low energy
|
||||
levels, this means that adjoint flux particles are typically sampled at a low
|
||||
energy and then upscatter (via a transposed scattering matrix) over their
|
||||
lifetimes.
|
||||
|
||||
In OpenMC, the random ray adjoint solver is implemented simply by transposing
|
||||
the scattering matrix, swapping :math:`\nu\Sigma_f` and :math:`\chi`, and then
|
||||
running a normal transport solve. When no external fixed source is present, no
|
||||
additional changes are needed in the transport process. However, if an external
|
||||
fixed forward source is present in the simulation problem, then an additional
|
||||
step is taken to compute the accompanying fixed adjoint source. In OpenMC, the
|
||||
adjoint flux does *not* represent a response function for a particular detector
|
||||
region. Rather, the adjoint flux is the global response, making it appropriate
|
||||
for use with weight window generation schemes for global variance reduction.
|
||||
Thus, if using a fixed source, the external source for the adjoint mode is
|
||||
simply computed as being :math:`1 / \phi`, where :math:`\phi` is the forward
|
||||
scalar flux that results from a normal forward solve (which OpenMC will run
|
||||
first automatically when in adjoint mode). The adjoint external source will be
|
||||
computed for each source region in the simulation mesh, independent of any
|
||||
tallies. The adjoint external source is always flat, even when a linear
|
||||
scattering and fission source shape is used. When in adjoint mode, all reported
|
||||
results (e.g., tallies, eigenvalues, etc.) are derived from the adjoint flux,
|
||||
even when the physical meaning is not necessarily obvious. These values are
|
||||
still reported, though we emphasize that the primary use case for adjoint mode
|
||||
is for producing adjoint flux tallies to support subsequent perturbation studies
|
||||
and weight window generation.
|
||||
|
||||
Note that the adjoint :math:`k_{eff}` is statistically the same as the forward
|
||||
:math:`k_{eff}`, despite the flux distributions taking different shapes.
|
||||
|
||||
---------------------------
|
||||
Fundamental Sources of Bias
|
||||
---------------------------
|
||||
|
|
|
|||
|
|
@ -558,7 +558,7 @@ following methods are currently available in OpenMC:
|
|||
- Cons
|
||||
* - ``simulation_averaged``
|
||||
- Accumulates total active ray lengths in each FSR over all iterations,
|
||||
improving the estimate of the volume in each cell each iteration.
|
||||
improving the estimate of the volume in each cell each iteration.
|
||||
- * Virtually unbiased after several iterations
|
||||
* Asymptotically approaches the true analytical volume
|
||||
* Typically most efficient in terms of speed vs. accuracy
|
||||
|
|
@ -593,6 +593,33 @@ estimator, the following code would be used:
|
|||
|
||||
settings.random_ray['volume_estimator'] = 'naive'
|
||||
|
||||
-----------------
|
||||
Adjoint Flux Mode
|
||||
-----------------
|
||||
|
||||
The adjoint flux random ray solver mode can be enabled as:
|
||||
entire
|
||||
::
|
||||
|
||||
settings.random_ray['adjoint'] = True
|
||||
|
||||
When enabled, OpenMC will first run a forward transport simulation followed by
|
||||
an adjoint transport simulation. The purpose of the forward solve is to compute
|
||||
the adjoint external source when an external source is present in the
|
||||
simulation. Simulation settings (e.g., number of rays, batches, etc.) will be
|
||||
identical for both simulations. At the conclusion of the run, all results (e.g.,
|
||||
tallies, plots, etc.) will be derived from the adjoint flux rather than the
|
||||
forward flux but are not labeled any differently. The initial forward flux
|
||||
solution will not be stored or available in the final statepoint file. Those
|
||||
wishing to do analysis requiring both the forward and adjoint solutions will
|
||||
need to run two separate simulations and load both statepoint files.
|
||||
|
||||
.. note::
|
||||
When adjoint mode is selected, OpenMC will always perform a full forward
|
||||
solve and then run a full adjoint solve immediately afterwards. Statepoint
|
||||
and tally results will be derived from the adjoint flux, but will not be
|
||||
labeled any differently.
|
||||
|
||||
---------------------------------------
|
||||
Putting it All Together: Example Inputs
|
||||
---------------------------------------
|
||||
|
|
|
|||
|
|
@ -86,8 +86,10 @@ public:
|
|||
bool fissionable; // Is this fissionable
|
||||
bool is_isotropic {
|
||||
true}; // used to skip search for angle indices if isotropic
|
||||
bool exists_in_model {true}; // Is this present in model
|
||||
|
||||
Mgxs() = default;
|
||||
Mgxs(bool exists) : exists_in_model(exists) {}
|
||||
|
||||
//! \brief Constructor that loads the Mgxs object from the HDF5 file
|
||||
//!
|
||||
|
|
|
|||
|
|
@ -111,13 +111,17 @@ public:
|
|||
virtual void all_reduce_replicated_source_regions();
|
||||
void convert_external_sources();
|
||||
void count_external_source_regions();
|
||||
void set_adjoint_sources(const vector<double>& forward_flux);
|
||||
virtual void flux_swap();
|
||||
virtual double evaluate_flux_at_point(Position r, int64_t sr, int g) const;
|
||||
double compute_fixed_source_normalization_factor() const;
|
||||
void flatten_xs();
|
||||
void transpose_scattering_matrix();
|
||||
|
||||
//----------------------------------------------------------------------------
|
||||
// Static Data members
|
||||
static bool volume_normalized_flux_tallies_;
|
||||
static bool adjoint_; // If the user wants outputs based on the adjoint flux
|
||||
|
||||
//----------------------------------------------------------------------------
|
||||
// Static data members
|
||||
|
|
@ -150,6 +154,19 @@ public:
|
|||
vector<float> source_;
|
||||
vector<float> external_source_;
|
||||
vector<bool> external_source_present_;
|
||||
vector<double> scalar_flux_final_;
|
||||
|
||||
// 2D arrays stored in 1D representing values for all materials x energy
|
||||
// groups
|
||||
int n_materials_;
|
||||
vector<double> sigma_t_;
|
||||
vector<double> nu_sigma_f_;
|
||||
vector<double> sigma_f_;
|
||||
vector<double> chi_;
|
||||
|
||||
// 3D arrays stored in 1D representing values for all materials x energy
|
||||
// groups x energy groups
|
||||
vector<double> sigma_s_;
|
||||
|
||||
protected:
|
||||
//----------------------------------------------------------------------------
|
||||
|
|
@ -190,10 +207,6 @@ protected:
|
|||
vector<int> material_;
|
||||
vector<double> volume_naive_;
|
||||
|
||||
// 2D arrays stored in 1D representing values for all source regions x energy
|
||||
// groups
|
||||
vector<float> scalar_flux_final_;
|
||||
|
||||
// Volumes for each tally and bin/score combination. This intermediate data
|
||||
// structure is used when tallying quantities that must be normalized by
|
||||
// volume (i.e., flux). The vector is index by tally index, while the inner 2D
|
||||
|
|
|
|||
|
|
@ -20,6 +20,8 @@ public:
|
|||
//----------------------------------------------------------------------------
|
||||
// Methods
|
||||
void compute_segment_correction_factors();
|
||||
void prepare_fixed_sources();
|
||||
void prepare_fixed_sources_adjoint(vector<double>& forward_flux);
|
||||
void simulate();
|
||||
void reduce_simulation_statistics();
|
||||
void output_simulation_results() const;
|
||||
|
|
@ -30,8 +32,13 @@ public:
|
|||
int64_t n_external_source_regions) const;
|
||||
|
||||
//----------------------------------------------------------------------------
|
||||
// Data members
|
||||
// Accessors
|
||||
FlatSourceDomain* domain() const { return domain_.get(); }
|
||||
|
||||
private:
|
||||
//----------------------------------------------------------------------------
|
||||
// Data members
|
||||
|
||||
// Contains all flat source region data
|
||||
unique_ptr<FlatSourceDomain> domain_;
|
||||
|
||||
|
|
|
|||
|
|
@ -208,7 +208,7 @@ class OpenMCOperator(TransportOperator):
|
|||
if nuclide in self.nuclides_with_data or self._decay_nucs:
|
||||
model_nuclides.add(nuclide)
|
||||
else:
|
||||
msg = (f"Nuclilde {nuclide} in material {mat.id} is not "
|
||||
msg = (f"Nuclide {nuclide} in material {mat.id} is not "
|
||||
"present in the depletion chain and has no cross "
|
||||
"section data.")
|
||||
warn(msg)
|
||||
|
|
|
|||
|
|
@ -170,6 +170,9 @@ class Settings:
|
|||
cm/cm^3. When disabled, flux tallies will be reported in units
|
||||
of cm (i.e., total distance traveled by neutrons in the spatial
|
||||
tally region).
|
||||
:adjoint:
|
||||
Whether to run the random ray solver in adjoint mode (bool). The
|
||||
default is 'False'.
|
||||
|
||||
.. versionadded:: 0.15.0
|
||||
resonance_scattering : dict
|
||||
|
|
@ -1113,6 +1116,8 @@ class Settings:
|
|||
('flat', 'linear', 'linear_xy'))
|
||||
elif key == 'volume_normalized_flux_tallies':
|
||||
cv.check_type('volume normalized flux tallies', random_ray[key], bool)
|
||||
elif key == 'adjoint':
|
||||
cv.check_type('adjoint', random_ray[key], bool)
|
||||
else:
|
||||
raise ValueError(f'Unable to set random ray to "{key}" which is '
|
||||
'unsupported by OpenMC')
|
||||
|
|
@ -1916,6 +1921,10 @@ class Settings:
|
|||
self.random_ray['volume_normalized_flux_tallies'] = (
|
||||
child.text in ('true', '1')
|
||||
)
|
||||
elif child.tag == 'adjoint':
|
||||
self.random_ray['adjoint'] = (
|
||||
child.text in ('true', '1')
|
||||
)
|
||||
|
||||
def to_xml_element(self, mesh_memo=None):
|
||||
"""Create a 'settings' element to be written to an XML file.
|
||||
|
|
|
|||
|
|
@ -146,7 +146,7 @@ void MgxsInterface::create_macro_xs()
|
|||
num_energy_groups_, num_delayed_groups_);
|
||||
} else {
|
||||
// Preserve the ordering of materials by including a blank entry
|
||||
macro_xs_.emplace_back();
|
||||
macro_xs_.emplace_back(false);
|
||||
}
|
||||
}
|
||||
}
|
||||
|
|
|
|||
|
|
@ -27,6 +27,7 @@ namespace openmc {
|
|||
RandomRayVolumeEstimator FlatSourceDomain::volume_estimator_ {
|
||||
RandomRayVolumeEstimator::HYBRID};
|
||||
bool FlatSourceDomain::volume_normalized_flux_tallies_ {false};
|
||||
bool FlatSourceDomain::adjoint_ {false};
|
||||
|
||||
FlatSourceDomain::FlatSourceDomain() : negroups_(data::mg.num_energy_groups_)
|
||||
{
|
||||
|
|
@ -134,31 +135,23 @@ void FlatSourceDomain::update_neutron_source(double k_eff)
|
|||
|
||||
double inverse_k_eff = 1.0 / k_eff;
|
||||
|
||||
// Temperature and angle indices, if using multiple temperature
|
||||
// data sets and/or anisotropic data sets.
|
||||
// TODO: Currently assumes we are only using single temp/single angle data.
|
||||
const int t = 0;
|
||||
const int a = 0;
|
||||
|
||||
// Add scattering source
|
||||
#pragma omp parallel for
|
||||
for (int sr = 0; sr < n_source_regions_; sr++) {
|
||||
int material = material_[sr];
|
||||
|
||||
for (int e_out = 0; e_out < negroups_; e_out++) {
|
||||
double sigma_t = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::TOTAL, e_out, nullptr, nullptr, nullptr, t, a);
|
||||
double scatter_source = 0.0f;
|
||||
for (int g_out = 0; g_out < negroups_; g_out++) {
|
||||
double sigma_t = sigma_t_[material * negroups_ + g_out];
|
||||
double scatter_source = 0.0;
|
||||
|
||||
for (int e_in = 0; e_in < negroups_; e_in++) {
|
||||
double scalar_flux = scalar_flux_old_[sr * negroups_ + e_in];
|
||||
|
||||
double sigma_s = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::NU_SCATTER, e_in, &e_out, nullptr, nullptr, t, a);
|
||||
for (int g_in = 0; g_in < negroups_; g_in++) {
|
||||
double scalar_flux = scalar_flux_old_[sr * negroups_ + g_in];
|
||||
double sigma_s =
|
||||
sigma_s_[material * negroups_ * negroups_ + g_out * negroups_ + g_in];
|
||||
scatter_source += sigma_s * scalar_flux;
|
||||
}
|
||||
|
||||
source_[sr * negroups_ + e_out] = scatter_source / sigma_t;
|
||||
source_[sr * negroups_ + g_out] = scatter_source / sigma_t;
|
||||
}
|
||||
}
|
||||
|
||||
|
|
@ -167,20 +160,17 @@ void FlatSourceDomain::update_neutron_source(double k_eff)
|
|||
for (int sr = 0; sr < n_source_regions_; sr++) {
|
||||
int material = material_[sr];
|
||||
|
||||
for (int e_out = 0; e_out < negroups_; e_out++) {
|
||||
double sigma_t = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::TOTAL, e_out, nullptr, nullptr, nullptr, t, a);
|
||||
double fission_source = 0.0f;
|
||||
for (int g_out = 0; g_out < negroups_; g_out++) {
|
||||
double sigma_t = sigma_t_[material * negroups_ + g_out];
|
||||
double fission_source = 0.0;
|
||||
|
||||
for (int e_in = 0; e_in < negroups_; e_in++) {
|
||||
double scalar_flux = scalar_flux_old_[sr * negroups_ + e_in];
|
||||
double nu_sigma_f = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::NU_FISSION, e_in, nullptr, nullptr, nullptr, t, a);
|
||||
double chi = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::CHI_PROMPT, e_in, &e_out, nullptr, nullptr, t, a);
|
||||
for (int g_in = 0; g_in < negroups_; g_in++) {
|
||||
double scalar_flux = scalar_flux_old_[sr * negroups_ + g_in];
|
||||
double nu_sigma_f = nu_sigma_f_[material * negroups_ + g_in];
|
||||
double chi = chi_[material * negroups_ + g_out];
|
||||
fission_source += nu_sigma_f * scalar_flux * chi;
|
||||
}
|
||||
source_[sr * negroups_ + e_out] +=
|
||||
source_[sr * negroups_ + g_out] +=
|
||||
fission_source * inverse_k_eff / sigma_t;
|
||||
}
|
||||
}
|
||||
|
|
@ -188,7 +178,7 @@ void FlatSourceDomain::update_neutron_source(double k_eff)
|
|||
// Add external source if in fixed source mode
|
||||
if (settings::run_mode == RunMode::FIXED_SOURCE) {
|
||||
#pragma omp parallel for
|
||||
for (int se = 0; se < n_source_elements_; se++) {
|
||||
for (int64_t se = 0; se < n_source_elements_; se++) {
|
||||
source_[se] += external_source_[se];
|
||||
}
|
||||
}
|
||||
|
|
@ -206,8 +196,8 @@ void FlatSourceDomain::normalize_scalar_flux_and_volumes(
|
|||
|
||||
// Normalize scalar flux to total distance travelled by all rays this iteration
|
||||
#pragma omp parallel for
|
||||
for (int64_t e = 0; e < scalar_flux_new_.size(); e++) {
|
||||
scalar_flux_new_[e] *= normalization_factor;
|
||||
for (int64_t se = 0; se < scalar_flux_new_.size(); se++) {
|
||||
scalar_flux_new_[se] *= normalization_factor;
|
||||
}
|
||||
|
||||
// Accumulate cell-wise ray length tallies collected this iteration, then
|
||||
|
|
@ -223,16 +213,7 @@ void FlatSourceDomain::normalize_scalar_flux_and_volumes(
|
|||
void FlatSourceDomain::set_flux_to_flux_plus_source(
|
||||
int64_t idx, double volume, int material, int g)
|
||||
{
|
||||
// Temperature and angle indices, if using multiple temperature
|
||||
// data sets and/or anisotropic data sets.
|
||||
// TODO: Currently assumes we are only using single temp/single
|
||||
// angle data.
|
||||
const int t = 0;
|
||||
const int a = 0;
|
||||
|
||||
double sigma_t = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::TOTAL, g, nullptr, nullptr, nullptr, t, a);
|
||||
|
||||
double sigma_t = sigma_t_[material * negroups_ + g];
|
||||
scalar_flux_new_[idx] /= (sigma_t * volume);
|
||||
scalar_flux_new_[idx] += source_[idx];
|
||||
}
|
||||
|
|
@ -337,13 +318,6 @@ double FlatSourceDomain::compute_k_eff(double k_eff_old) const
|
|||
double fission_rate_old = 0;
|
||||
double fission_rate_new = 0;
|
||||
|
||||
// Temperature and angle indices, if using multiple temperature
|
||||
// data sets and/or anisotropic data sets.
|
||||
// TODO: Currently assumes we are only using single temp/single
|
||||
// angle data.
|
||||
const int t = 0;
|
||||
const int a = 0;
|
||||
|
||||
// Vector for gathering fission source terms for Shannon entropy calculation
|
||||
vector<float> p(n_source_regions_, 0.0f);
|
||||
|
||||
|
|
@ -363,8 +337,7 @@ double FlatSourceDomain::compute_k_eff(double k_eff_old) const
|
|||
|
||||
for (int g = 0; g < negroups_; g++) {
|
||||
int64_t idx = (sr * negroups_) + g;
|
||||
double nu_sigma_f = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::NU_FISSION, g, nullptr, nullptr, nullptr, t, a);
|
||||
double nu_sigma_f = nu_sigma_f_[material * negroups_ + g];
|
||||
sr_fission_source_old += nu_sigma_f * scalar_flux_old_[idx];
|
||||
sr_fission_source_new += nu_sigma_f * scalar_flux_new_[idx];
|
||||
}
|
||||
|
|
@ -548,7 +521,7 @@ double FlatSourceDomain::compute_fixed_source_normalization_factor() const
|
|||
{
|
||||
// If we are not in fixed source mode, then there are no external sources
|
||||
// so no normalization is needed.
|
||||
if (settings::run_mode != RunMode::FIXED_SOURCE) {
|
||||
if (settings::run_mode != RunMode::FIXED_SOURCE || adjoint_) {
|
||||
return 1.0;
|
||||
}
|
||||
|
||||
|
|
@ -559,17 +532,10 @@ double FlatSourceDomain::compute_fixed_source_normalization_factor() const
|
|||
for (int sr = 0; sr < n_source_regions_; sr++) {
|
||||
int material = material_[sr];
|
||||
double volume = volume_[sr] * simulation_volume_;
|
||||
for (int e = 0; e < negroups_; e++) {
|
||||
// Temperature and angle indices, if using multiple temperature
|
||||
// data sets and/or anisotropic data sets.
|
||||
// TODO: Currently assumes we are only using single temp/single
|
||||
// angle data.
|
||||
const int t = 0;
|
||||
const int a = 0;
|
||||
double sigma_t = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::TOTAL, e, nullptr, nullptr, nullptr, t, a);
|
||||
for (int g = 0; g < negroups_; g++) {
|
||||
double sigma_t = sigma_t_[material * negroups_ + g];
|
||||
simulation_external_source_strength +=
|
||||
external_source_[sr * negroups_ + e] * sigma_t * volume;
|
||||
external_source_[sr * negroups_ + g] * sigma_t * volume;
|
||||
}
|
||||
}
|
||||
|
||||
|
|
@ -603,13 +569,6 @@ void FlatSourceDomain::random_ray_tally()
|
|||
// Reset our tally volumes to zero
|
||||
reset_tally_volumes();
|
||||
|
||||
// Temperature and angle indices, if using multiple temperature
|
||||
// data sets and/or anisotropic data sets.
|
||||
// TODO: Currently assumes we are only using single temp/single
|
||||
// angle data.
|
||||
const int t = 0;
|
||||
const int a = 0;
|
||||
|
||||
double source_normalization_factor =
|
||||
compute_fixed_source_normalization_factor();
|
||||
|
||||
|
|
@ -644,21 +603,15 @@ void FlatSourceDomain::random_ray_tally()
|
|||
break;
|
||||
|
||||
case SCORE_TOTAL:
|
||||
score = flux * volume *
|
||||
data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::TOTAL, g, NULL, NULL, NULL, t, a);
|
||||
score = flux * volume * sigma_t_[material * negroups_ + g];
|
||||
break;
|
||||
|
||||
case SCORE_FISSION:
|
||||
score = flux * volume *
|
||||
data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::FISSION, g, NULL, NULL, NULL, t, a);
|
||||
score = flux * volume * sigma_f_[material * negroups_ + g];
|
||||
break;
|
||||
|
||||
case SCORE_NU_FISSION:
|
||||
score = flux * volume *
|
||||
data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::NU_FISSION, g, NULL, NULL, NULL, t, a);
|
||||
score = flux * volume * nu_sigma_f_[material * negroups_ + g];
|
||||
break;
|
||||
|
||||
case SCORE_EVENTS:
|
||||
|
|
@ -957,9 +910,8 @@ void FlatSourceDomain::output_to_vtk() const
|
|||
for (int g = 0; g < negroups_; g++) {
|
||||
int64_t source_element = fsr * negroups_ + g;
|
||||
float flux = evaluate_flux_at_point(voxel_positions[i], fsr, g);
|
||||
float Sigma_f = data::mg.macro_xs_[mat].get_xs(
|
||||
MgxsType::FISSION, g, nullptr, nullptr, nullptr, 0, 0);
|
||||
total_fission += Sigma_f * flux;
|
||||
double sigma_f = sigma_f_[mat * negroups_ + g];
|
||||
total_fission += sigma_f * flux;
|
||||
}
|
||||
total_fission = convert_to_big_endian<float>(total_fission);
|
||||
std::fwrite(&total_fission, sizeof(float), 1, plot);
|
||||
|
|
@ -977,10 +929,10 @@ void FlatSourceDomain::apply_external_source_to_source_region(
|
|||
const auto& discrete_energies = discrete->x();
|
||||
const auto& discrete_probs = discrete->prob();
|
||||
|
||||
for (int e = 0; e < discrete_energies.size(); e++) {
|
||||
int g = data::mg.get_group_index(discrete_energies[e]);
|
||||
for (int i = 0; i < discrete_energies.size(); i++) {
|
||||
int g = data::mg.get_group_index(discrete_energies[i]);
|
||||
external_source_[source_region * negroups_ + g] +=
|
||||
discrete_probs[e] * strength_factor;
|
||||
discrete_probs[i] * strength_factor;
|
||||
}
|
||||
}
|
||||
|
||||
|
|
@ -1074,27 +1026,107 @@ void FlatSourceDomain::convert_external_sources()
|
|||
}
|
||||
} // End loop over external sources
|
||||
|
||||
// Divide the fixed source term by sigma t (to save time when applying each
|
||||
// iteration)
|
||||
#pragma omp parallel for
|
||||
for (int sr = 0; sr < n_source_regions_; sr++) {
|
||||
int material = material_[sr];
|
||||
for (int g = 0; g < negroups_; g++) {
|
||||
double sigma_t = sigma_t_[material * negroups_ + g];
|
||||
external_source_[sr * negroups_ + g] /= sigma_t;
|
||||
}
|
||||
}
|
||||
}
|
||||
|
||||
void FlatSourceDomain::flux_swap()
|
||||
{
|
||||
scalar_flux_old_.swap(scalar_flux_new_);
|
||||
}
|
||||
|
||||
void FlatSourceDomain::flatten_xs()
|
||||
{
|
||||
// Temperature and angle indices, if using multiple temperature
|
||||
// data sets and/or anisotropic data sets.
|
||||
// TODO: Currently assumes we are only using single temp/single angle data.
|
||||
const int t = 0;
|
||||
const int a = 0;
|
||||
|
||||
// Divide the fixed source term by sigma t (to save time when applying each
|
||||
// iteration)
|
||||
#pragma omp parallel for
|
||||
for (int sr = 0; sr < n_source_regions_; sr++) {
|
||||
int material = material_[sr];
|
||||
for (int e = 0; e < negroups_; e++) {
|
||||
double sigma_t = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::TOTAL, e, nullptr, nullptr, nullptr, t, a);
|
||||
external_source_[sr * negroups_ + e] /= sigma_t;
|
||||
n_materials_ = data::mg.macro_xs_.size();
|
||||
for (auto& m : data::mg.macro_xs_) {
|
||||
for (int g_out = 0; g_out < negroups_; g_out++) {
|
||||
if (m.exists_in_model) {
|
||||
double sigma_t =
|
||||
m.get_xs(MgxsType::TOTAL, g_out, NULL, NULL, NULL, t, a);
|
||||
sigma_t_.push_back(sigma_t);
|
||||
|
||||
double nu_Sigma_f =
|
||||
m.get_xs(MgxsType::NU_FISSION, g_out, NULL, NULL, NULL, t, a);
|
||||
nu_sigma_f_.push_back(nu_Sigma_f);
|
||||
|
||||
double sigma_f =
|
||||
m.get_xs(MgxsType::FISSION, g_out, NULL, NULL, NULL, t, a);
|
||||
sigma_f_.push_back(sigma_f);
|
||||
|
||||
double chi =
|
||||
m.get_xs(MgxsType::CHI_PROMPT, g_out, &g_out, NULL, NULL, t, a);
|
||||
chi_.push_back(chi);
|
||||
|
||||
for (int g_in = 0; g_in < negroups_; g_in++) {
|
||||
double sigma_s =
|
||||
m.get_xs(MgxsType::NU_SCATTER, g_in, &g_out, NULL, NULL, t, a);
|
||||
sigma_s_.push_back(sigma_s);
|
||||
}
|
||||
} else {
|
||||
sigma_t_.push_back(0);
|
||||
nu_sigma_f_.push_back(0);
|
||||
sigma_f_.push_back(0);
|
||||
chi_.push_back(0);
|
||||
for (int g_in = 0; g_in < negroups_; g_in++) {
|
||||
sigma_s_.push_back(0);
|
||||
}
|
||||
}
|
||||
}
|
||||
}
|
||||
}
|
||||
void FlatSourceDomain::flux_swap()
|
||||
|
||||
void FlatSourceDomain::set_adjoint_sources(const vector<double>& forward_flux)
|
||||
{
|
||||
scalar_flux_old_.swap(scalar_flux_new_);
|
||||
// Set the external source to 1/forward_flux
|
||||
// The forward flux is given in terms of total for the forward simulation
|
||||
// so we must convert it to a "per batch" quantity
|
||||
#pragma omp parallel for
|
||||
for (int64_t se = 0; se < n_source_elements_; se++) {
|
||||
external_source_[se] = 1.0 / forward_flux[se];
|
||||
}
|
||||
|
||||
// Divide the fixed source term by sigma t (to save time when applying each
|
||||
// iteration)
|
||||
#pragma omp parallel for
|
||||
for (int sr = 0; sr < n_source_regions_; sr++) {
|
||||
int material = material_[sr];
|
||||
for (int g = 0; g < negroups_; g++) {
|
||||
double sigma_t = sigma_t_[material * negroups_ + g];
|
||||
external_source_[sr * negroups_ + g] /= sigma_t;
|
||||
}
|
||||
}
|
||||
}
|
||||
|
||||
void FlatSourceDomain::transpose_scattering_matrix()
|
||||
{
|
||||
// Transpose the inner two dimensions for each material
|
||||
for (int m = 0; m < n_materials_; ++m) {
|
||||
int material_offset = m * negroups_ * negroups_;
|
||||
for (int i = 0; i < negroups_; ++i) {
|
||||
for (int j = i + 1; j < negroups_; ++j) {
|
||||
// Calculate indices of the elements to swap
|
||||
int idx1 = material_offset + i * negroups_ + j;
|
||||
int idx2 = material_offset + j * negroups_ + i;
|
||||
|
||||
// Swap the elements to transpose the matrix
|
||||
std::swap(sigma_s_[idx1], sigma_s_[idx2]);
|
||||
}
|
||||
}
|
||||
}
|
||||
}
|
||||
|
||||
} // namespace openmc
|
||||
|
|
|
|||
|
|
@ -56,40 +56,30 @@ void LinearSourceDomain::update_neutron_source(double k_eff)
|
|||
|
||||
double inverse_k_eff = 1.0 / k_eff;
|
||||
|
||||
// Temperature and angle indices, if using multiple temperature
|
||||
// data sets and/or anisotropic data sets.
|
||||
// TODO: Currently assumes we are only using single temp/single
|
||||
// angle data.
|
||||
const int t = 0;
|
||||
const int a = 0;
|
||||
|
||||
#pragma omp parallel for
|
||||
for (int sr = 0; sr < n_source_regions_; sr++) {
|
||||
|
||||
int material = material_[sr];
|
||||
MomentMatrix invM = mom_matrix_[sr].inverse();
|
||||
|
||||
for (int e_out = 0; e_out < negroups_; e_out++) {
|
||||
double sigma_t = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::TOTAL, e_out, nullptr, nullptr, nullptr, t, a);
|
||||
for (int g_out = 0; g_out < negroups_; g_out++) {
|
||||
double sigma_t = sigma_t_[material * negroups_ + g_out];
|
||||
|
||||
double scatter_flat = 0.0f;
|
||||
double fission_flat = 0.0f;
|
||||
MomentArray scatter_linear = {0.0, 0.0, 0.0};
|
||||
MomentArray fission_linear = {0.0, 0.0, 0.0};
|
||||
|
||||
for (int e_in = 0; e_in < negroups_; e_in++) {
|
||||
for (int g_in = 0; g_in < negroups_; g_in++) {
|
||||
// Handles for the flat and linear components of the flux
|
||||
double flux_flat = scalar_flux_old_[sr * negroups_ + e_in];
|
||||
MomentArray flux_linear = flux_moments_old_[sr * negroups_ + e_in];
|
||||
double flux_flat = scalar_flux_old_[sr * negroups_ + g_in];
|
||||
MomentArray flux_linear = flux_moments_old_[sr * negroups_ + g_in];
|
||||
|
||||
// Handles for cross sections
|
||||
double sigma_s = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::NU_SCATTER, e_in, &e_out, nullptr, nullptr, t, a);
|
||||
double nu_sigma_f = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::NU_FISSION, e_in, nullptr, nullptr, nullptr, t, a);
|
||||
double chi = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::CHI_PROMPT, e_in, &e_out, nullptr, nullptr, t, a);
|
||||
double sigma_s =
|
||||
sigma_s_[material * negroups_ * negroups_ + g_out * negroups_ + g_in];
|
||||
double nu_sigma_f = nu_sigma_f_[material * negroups_ + g_in];
|
||||
double chi = chi_[material * negroups_ + g_out];
|
||||
|
||||
// Compute source terms for flat and linear components of the flux
|
||||
scatter_flat += sigma_s * flux_flat;
|
||||
|
|
@ -99,7 +89,7 @@ void LinearSourceDomain::update_neutron_source(double k_eff)
|
|||
}
|
||||
|
||||
// Compute the flat source term
|
||||
source_[sr * negroups_ + e_out] =
|
||||
source_[sr * negroups_ + g_out] =
|
||||
(scatter_flat + fission_flat * inverse_k_eff) / sigma_t;
|
||||
|
||||
// Compute the linear source terms
|
||||
|
|
@ -107,7 +97,7 @@ void LinearSourceDomain::update_neutron_source(double k_eff)
|
|||
// are not well known, we will leave the source gradients as zero
|
||||
// so as to avoid causing any numerical instability.
|
||||
if (simulation::current_batch > 10) {
|
||||
source_gradients_[sr * negroups_ + e_out] =
|
||||
source_gradients_[sr * negroups_ + g_out] =
|
||||
invM * ((scatter_linear + fission_linear * inverse_k_eff) / sigma_t);
|
||||
}
|
||||
}
|
||||
|
|
@ -116,7 +106,7 @@ void LinearSourceDomain::update_neutron_source(double k_eff)
|
|||
if (settings::run_mode == RunMode::FIXED_SOURCE) {
|
||||
// Add external source to flat source term if in fixed source mode
|
||||
#pragma omp parallel for
|
||||
for (int se = 0; se < n_source_elements_; se++) {
|
||||
for (int64_t se = 0; se < n_source_elements_; se++) {
|
||||
source_[se] += external_source_[se];
|
||||
}
|
||||
}
|
||||
|
|
@ -133,9 +123,9 @@ void LinearSourceDomain::normalize_scalar_flux_and_volumes(
|
|||
|
||||
// Normalize flux to total distance travelled by all rays this iteration
|
||||
#pragma omp parallel for
|
||||
for (int64_t e = 0; e < scalar_flux_new_.size(); e++) {
|
||||
scalar_flux_new_[e] *= normalization_factor;
|
||||
flux_moments_new_[e] *= normalization_factor;
|
||||
for (int64_t se = 0; se < scalar_flux_new_.size(); se++) {
|
||||
scalar_flux_new_[se] *= normalization_factor;
|
||||
flux_moments_new_[se] *= normalization_factor;
|
||||
}
|
||||
|
||||
// Accumulate cell-wise ray length tallies collected this iteration, then
|
||||
|
|
|
|||
|
|
@ -316,17 +316,9 @@ void RandomRay::attenuate_flux_flat_source(double distance, bool is_active)
|
|||
int64_t source_element = source_region * negroups_;
|
||||
int material = this->material();
|
||||
|
||||
// Temperature and angle indices, if using multiple temperature
|
||||
// data sets and/or anisotropic data sets.
|
||||
// TODO: Currently assumes we are only using single temp/single
|
||||
// angle data.
|
||||
const int t = 0;
|
||||
const int a = 0;
|
||||
|
||||
// MOC incoming flux attenuation + source contribution/attenuation equation
|
||||
for (int g = 0; g < negroups_; g++) {
|
||||
float sigma_t = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::TOTAL, g, NULL, NULL, NULL, t, a);
|
||||
float sigma_t = domain_->sigma_t_[material * negroups_ + g];
|
||||
float tau = sigma_t * distance;
|
||||
float exponential = cjosey_exponential(tau); // exponential = 1 - exp(-tau)
|
||||
float new_delta_psi =
|
||||
|
|
@ -388,13 +380,6 @@ void RandomRay::attenuate_flux_linear_source(double distance, bool is_active)
|
|||
int64_t source_element = source_region * negroups_;
|
||||
int material = this->material();
|
||||
|
||||
// Temperature and angle indices, if using multiple temperature
|
||||
// data sets and/or anisotropic data sets.
|
||||
// TODO: Currently assumes we are only using single temp/single
|
||||
// angle data.
|
||||
const int t = 0;
|
||||
const int a = 0;
|
||||
|
||||
Position& centroid = domain->centroid_[source_region];
|
||||
Position midpoint = r() + u() * (distance / 2.0);
|
||||
|
||||
|
|
@ -422,8 +407,7 @@ void RandomRay::attenuate_flux_linear_source(double distance, bool is_active)
|
|||
for (int g = 0; g < negroups_; g++) {
|
||||
|
||||
// Compute tau, the optical thickness of the ray segment
|
||||
float sigma_t = data::mg.macro_xs_[material].get_xs(
|
||||
MgxsType::TOTAL, g, NULL, NULL, NULL, t, a);
|
||||
float sigma_t = domain_->sigma_t_[material * negroups_ + g];
|
||||
float tau = sigma_t * distance;
|
||||
|
||||
// If tau is very small, set it to zero to avoid numerical issues.
|
||||
|
|
|
|||
|
|
@ -23,6 +23,22 @@ namespace openmc {
|
|||
|
||||
void openmc_run_random_ray()
|
||||
{
|
||||
//////////////////////////////////////////////////////////
|
||||
// Run forward simulation
|
||||
//////////////////////////////////////////////////////////
|
||||
|
||||
// Check if adjoint calculation is needed. If it is, we will run the forward
|
||||
// calculation first and then the adjoint calculation later.
|
||||
bool adjoint_needed = FlatSourceDomain::adjoint_;
|
||||
|
||||
// Configure the domain for forward simulation
|
||||
FlatSourceDomain::adjoint_ = false;
|
||||
|
||||
// If we're going to do an adjoint simulation afterwards, report that this is
|
||||
// the initial forward flux solve.
|
||||
if (adjoint_needed && mpi::master)
|
||||
header("FORWARD FLUX SOLVE", 3);
|
||||
|
||||
// Initialize OpenMC general data structures
|
||||
openmc_simulation_init();
|
||||
|
||||
|
|
@ -30,26 +46,93 @@ void openmc_run_random_ray()
|
|||
if (mpi::master)
|
||||
validate_random_ray_inputs();
|
||||
|
||||
// Initialize Random Ray Simulation Object
|
||||
RandomRaySimulation sim;
|
||||
// Declare forward flux so that it can be saved for later adjoint simulation
|
||||
vector<double> forward_flux;
|
||||
|
||||
// Begin main simulation timer
|
||||
simulation::time_total.start();
|
||||
{
|
||||
// Initialize Random Ray Simulation Object
|
||||
RandomRaySimulation sim;
|
||||
|
||||
// Execute random ray simulation
|
||||
sim.simulate();
|
||||
// Initialize fixed sources, if present
|
||||
sim.prepare_fixed_sources();
|
||||
|
||||
// End main simulation timer
|
||||
openmc::simulation::time_total.stop();
|
||||
// Begin main simulation timer
|
||||
simulation::time_total.start();
|
||||
|
||||
// Finalize OpenMC
|
||||
openmc_simulation_finalize();
|
||||
// Execute random ray simulation
|
||||
sim.simulate();
|
||||
|
||||
// Reduce variables across MPI ranks
|
||||
sim.reduce_simulation_statistics();
|
||||
// End main simulation timer
|
||||
simulation::time_total.stop();
|
||||
|
||||
// Output all simulation results
|
||||
sim.output_simulation_results();
|
||||
// Normalize and save the final forward flux
|
||||
forward_flux = sim.domain()->scalar_flux_final_;
|
||||
|
||||
double source_normalization_factor =
|
||||
sim.domain()->compute_fixed_source_normalization_factor() /
|
||||
(settings::n_batches - settings::n_inactive);
|
||||
|
||||
#pragma omp parallel for
|
||||
for (uint64_t i = 0; i < forward_flux.size(); i++) {
|
||||
forward_flux[i] *= source_normalization_factor;
|
||||
}
|
||||
|
||||
// Finalize OpenMC
|
||||
openmc_simulation_finalize();
|
||||
|
||||
// Reduce variables across MPI ranks
|
||||
sim.reduce_simulation_statistics();
|
||||
|
||||
// Output all simulation results
|
||||
sim.output_simulation_results();
|
||||
}
|
||||
|
||||
//////////////////////////////////////////////////////////
|
||||
// Run adjoint simulation (if enabled)
|
||||
//////////////////////////////////////////////////////////
|
||||
|
||||
if (adjoint_needed) {
|
||||
reset_timers();
|
||||
|
||||
// Configure the domain for adjoint simulation
|
||||
FlatSourceDomain::adjoint_ = true;
|
||||
|
||||
if (mpi::master)
|
||||
header("ADJOINT FLUX SOLVE", 3);
|
||||
|
||||
// Initialize OpenMC general data structures
|
||||
openmc_simulation_init();
|
||||
|
||||
// Initialize Random Ray Simulation Object
|
||||
RandomRaySimulation adjoint_sim;
|
||||
|
||||
// Initialize adjoint fixed sources, if present
|
||||
adjoint_sim.prepare_fixed_sources_adjoint(forward_flux);
|
||||
|
||||
// Transpose scattering matrix
|
||||
adjoint_sim.domain()->transpose_scattering_matrix();
|
||||
|
||||
// Swap nu_sigma_f and chi
|
||||
adjoint_sim.domain()->nu_sigma_f_.swap(adjoint_sim.domain()->chi_);
|
||||
|
||||
// Begin main simulation timer
|
||||
simulation::time_total.start();
|
||||
|
||||
// Execute random ray simulation
|
||||
adjoint_sim.simulate();
|
||||
|
||||
// End main simulation timer
|
||||
simulation::time_total.stop();
|
||||
|
||||
// Finalize OpenMC
|
||||
openmc_simulation_finalize();
|
||||
|
||||
// Reduce variables across MPI ranks
|
||||
adjoint_sim.reduce_simulation_statistics();
|
||||
|
||||
// Output all simulation results
|
||||
adjoint_sim.output_simulation_results();
|
||||
}
|
||||
}
|
||||
|
||||
// Enforces restrictions on inputs in random ray mode. While there are
|
||||
|
|
@ -254,16 +337,31 @@ RandomRaySimulation::RandomRaySimulation()
|
|||
default:
|
||||
fatal_error("Unknown random ray source shape");
|
||||
}
|
||||
|
||||
// Convert OpenMC native MGXS into a more efficient format
|
||||
// internal to the random ray solver
|
||||
domain_->flatten_xs();
|
||||
}
|
||||
|
||||
void RandomRaySimulation::simulate()
|
||||
void RandomRaySimulation::prepare_fixed_sources()
|
||||
{
|
||||
if (settings::run_mode == RunMode::FIXED_SOURCE) {
|
||||
// Transfer external source user inputs onto random ray source regions
|
||||
domain_->convert_external_sources();
|
||||
domain_->count_external_source_regions();
|
||||
}
|
||||
}
|
||||
|
||||
void RandomRaySimulation::prepare_fixed_sources_adjoint(
|
||||
vector<double>& forward_flux)
|
||||
{
|
||||
if (settings::run_mode == RunMode::FIXED_SOURCE) {
|
||||
domain_->set_adjoint_sources(forward_flux);
|
||||
}
|
||||
}
|
||||
|
||||
void RandomRaySimulation::simulate()
|
||||
{
|
||||
// Random ray power iteration loop
|
||||
while (simulation::current_batch < settings::n_batches) {
|
||||
|
||||
|
|
@ -314,18 +412,20 @@ void RandomRaySimulation::simulate()
|
|||
}
|
||||
|
||||
// Execute all tallying tasks, if this is an active batch
|
||||
if (simulation::current_batch > settings::n_inactive && mpi::master) {
|
||||
|
||||
// Generate mapping between source regions and tallies
|
||||
if (!domain_->mapped_all_tallies_) {
|
||||
domain_->convert_source_regions_to_tallies();
|
||||
}
|
||||
|
||||
// Use above mapping to contribute FSR flux data to appropriate tallies
|
||||
domain_->random_ray_tally();
|
||||
if (simulation::current_batch > settings::n_inactive) {
|
||||
|
||||
// Add this iteration's scalar flux estimate to final accumulated estimate
|
||||
domain_->accumulate_iteration_flux();
|
||||
|
||||
if (mpi::master) {
|
||||
// Generate mapping between source regions and tallies
|
||||
if (!domain_->mapped_all_tallies_) {
|
||||
domain_->convert_source_regions_to_tallies();
|
||||
}
|
||||
|
||||
// Use above mapping to contribute FSR flux data to appropriate tallies
|
||||
domain_->random_ray_tally();
|
||||
}
|
||||
}
|
||||
|
||||
// Set phi_old = phi_new
|
||||
|
|
@ -448,6 +548,9 @@ void RandomRaySimulation::print_results_random_ray(
|
|||
}
|
||||
fmt::print(" Volume Estimator Type = {}\n", estimator);
|
||||
|
||||
std::string adjoint_true = (FlatSourceDomain::adjoint_) ? "ON" : "OFF";
|
||||
fmt::print(" Adjoint Flux Mode = {}\n", adjoint_true);
|
||||
|
||||
header("Timing Statistics", 4);
|
||||
show_time("Total time for initialization", time_initialize.elapsed());
|
||||
show_time("Reading cross sections", time_read_xs.elapsed(), 1);
|
||||
|
|
|
|||
|
|
@ -301,6 +301,10 @@ void get_run_parameters(pugi::xml_node node_base)
|
|||
FlatSourceDomain::volume_normalized_flux_tallies_ =
|
||||
get_node_value_bool(random_ray_node, "volume_normalized_flux_tallies");
|
||||
}
|
||||
if (check_for_node(random_ray_node, "adjoint")) {
|
||||
FlatSourceDomain::adjoint_ =
|
||||
get_node_value_bool(random_ray_node, "adjoint");
|
||||
}
|
||||
}
|
||||
}
|
||||
|
||||
|
|
|
|||
|
|
@ -0,0 +1,245 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<model>
|
||||
<materials>
|
||||
<cross_sections>mgxs.h5</cross_sections>
|
||||
<material id="1" name="source">
|
||||
<density units="macro" value="1.0"/>
|
||||
<macroscopic name="source"/>
|
||||
</material>
|
||||
<material id="2" name="void">
|
||||
<density units="macro" value="1.0"/>
|
||||
<macroscopic name="void"/>
|
||||
</material>
|
||||
<material id="3" name="absorber">
|
||||
<density units="macro" value="1.0"/>
|
||||
<macroscopic name="absorber"/>
|
||||
</material>
|
||||
</materials>
|
||||
<geometry>
|
||||
<cell id="1" material="1" name="infinite source region" universe="1"/>
|
||||
<cell id="2" material="2" name="infinite void region" universe="2"/>
|
||||
<cell id="3" material="3" name="infinite absorber region" universe="3"/>
|
||||
<cell fill="4" id="4" universe="5"/>
|
||||
<cell fill="5" id="5" name="full domain" region="1 -2 3 -4 5 -6" universe="6"/>
|
||||
<lattice id="4">
|
||||
<pitch>2.5 2.5 2.5</pitch>
|
||||
<dimension>12 12 12</dimension>
|
||||
<lower_left>0.0 0.0 0.0</lower_left>
|
||||
<universes>
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
1 1 2 2 2 2 2 2 2 2 3 3
|
||||
1 1 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
1 1 2 2 2 2 2 2 2 2 3 3
|
||||
1 1 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
2 2 2 2 2 2 2 2 2 2 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 3 3 </universes>
|
||||
</lattice>
|
||||
<surface boundary="reflective" coeffs="0.0" id="1" type="x-plane"/>
|
||||
<surface boundary="vacuum" coeffs="30.0" id="2" type="x-plane"/>
|
||||
<surface boundary="reflective" coeffs="0.0" id="3" type="y-plane"/>
|
||||
<surface boundary="vacuum" coeffs="30.0" id="4" type="y-plane"/>
|
||||
<surface boundary="reflective" coeffs="0.0" id="5" type="z-plane"/>
|
||||
<surface boundary="vacuum" coeffs="30.0" id="6" type="z-plane"/>
|
||||
</geometry>
|
||||
<settings>
|
||||
<run_mode>fixed source</run_mode>
|
||||
<particles>90</particles>
|
||||
<batches>10</batches>
|
||||
<inactive>5</inactive>
|
||||
<source particle="neutron" strength="3.14" type="independent">
|
||||
<energy type="discrete">
|
||||
<parameters>100.0 1.0</parameters>
|
||||
</energy>
|
||||
<constraints>
|
||||
<domain_type>universe</domain_type>
|
||||
<domain_ids>1</domain_ids>
|
||||
</constraints>
|
||||
</source>
|
||||
<energy_mode>multi-group</energy_mode>
|
||||
<random_ray>
|
||||
<distance_active>500.0</distance_active>
|
||||
<distance_inactive>100.0</distance_inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="box">
|
||||
<parameters>0.0 0.0 0.0 30.0 30.0 30.0</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<volume_normalized_flux_tallies>True</volume_normalized_flux_tallies>
|
||||
<adjoint>True</adjoint>
|
||||
</random_ray>
|
||||
</settings>
|
||||
<tallies>
|
||||
<filter id="3" type="material">
|
||||
<bins>1</bins>
|
||||
</filter>
|
||||
<filter id="2" type="material">
|
||||
<bins>2</bins>
|
||||
</filter>
|
||||
<filter id="1" type="material">
|
||||
<bins>3</bins>
|
||||
</filter>
|
||||
<tally id="3" name="Source Tally">
|
||||
<filters>3</filters>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="2" name="Void Tally">
|
||||
<filters>2</filters>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
<tally id="1" name="Absorber Tally">
|
||||
<filters>1</filters>
|
||||
<scores>flux</scores>
|
||||
<estimator>tracklength</estimator>
|
||||
</tally>
|
||||
</tallies>
|
||||
</model>
|
||||
|
|
@ -0,0 +1,9 @@
|
|||
tally 1:
|
||||
-7.235364E+03
|
||||
3.367109E+09
|
||||
tally 2:
|
||||
4.818311E+05
|
||||
6.269371E+10
|
||||
tally 3:
|
||||
1.515641E+06
|
||||
4.598791E+11
|
||||
|
|
@ -0,0 +1,20 @@
|
|||
import os
|
||||
|
||||
from openmc.examples import random_ray_three_region_cube
|
||||
|
||||
from tests.testing_harness import TolerantPyAPITestHarness
|
||||
|
||||
|
||||
class MGXSTestHarness(TolerantPyAPITestHarness):
|
||||
def _cleanup(self):
|
||||
super()._cleanup()
|
||||
f = 'mgxs.h5'
|
||||
if os.path.exists(f):
|
||||
os.remove(f)
|
||||
|
||||
|
||||
def test_random_ray_adjoint_fixed_source():
|
||||
model = random_ray_three_region_cube()
|
||||
model.settings.random_ray['adjoint'] = True
|
||||
harness = MGXSTestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
110
tests/regression_tests/random_ray_adjoint_k_eff/inputs_true.dat
Normal file
110
tests/regression_tests/random_ray_adjoint_k_eff/inputs_true.dat
Normal file
|
|
@ -0,0 +1,110 @@
|
|||
<?xml version='1.0' encoding='utf-8'?>
|
||||
<model>
|
||||
<materials>
|
||||
<cross_sections>mgxs.h5</cross_sections>
|
||||
<material id="1" name="UO2 fuel">
|
||||
<density units="macro" value="1.0"/>
|
||||
<macroscopic name="UO2"/>
|
||||
</material>
|
||||
<material id="2" name="Water">
|
||||
<density units="macro" value="1.0"/>
|
||||
<macroscopic name="LWTR"/>
|
||||
</material>
|
||||
</materials>
|
||||
<geometry>
|
||||
<cell id="1" material="1" name="fuel inner a" region="-2" universe="1"/>
|
||||
<cell id="2" material="1" name="fuel inner b" region="2 -3" universe="1"/>
|
||||
<cell id="3" material="1" name="fuel inner c" region="3 -1" universe="1"/>
|
||||
<cell id="4" material="2" name="moderator inner a" region="1 -4" universe="1"/>
|
||||
<cell id="5" material="2" name="moderator outer b" region="4 -5" universe="1"/>
|
||||
<cell id="6" material="2" name="moderator outer c" region="5" universe="1"/>
|
||||
<cell fill="1" id="7" name="azimuthal_cell_0" region="6 -7" universe="2"/>
|
||||
<cell fill="1" id="8" name="azimuthal_cell_1" region="7 -8" universe="2"/>
|
||||
<cell fill="1" id="9" name="azimuthal_cell_2" region="8 -9" universe="2"/>
|
||||
<cell fill="1" id="10" name="azimuthal_cell_3" region="9 -10" universe="2"/>
|
||||
<cell fill="1" id="11" name="azimuthal_cell_4" region="10 -11" universe="2"/>
|
||||
<cell fill="1" id="12" name="azimuthal_cell_5" region="11 -12" universe="2"/>
|
||||
<cell fill="1" id="13" name="azimuthal_cell_6" region="12 -13" universe="2"/>
|
||||
<cell fill="1" id="14" name="azimuthal_cell_7" region="13 -6" universe="2"/>
|
||||
<cell id="15" material="2" name="moderator infinite" universe="3"/>
|
||||
<cell fill="4" id="16" universe="5"/>
|
||||
<cell fill="6" id="17" name="assembly" region="14 -15 16 -17" universe="7"/>
|
||||
<lattice id="4">
|
||||
<pitch>0.126 0.126</pitch>
|
||||
<dimension>10 10</dimension>
|
||||
<lower_left>-0.63 -0.63</lower_left>
|
||||
<universes>
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3
|
||||
3 3 3 3 3 3 3 3 3 3 </universes>
|
||||
</lattice>
|
||||
<lattice id="6">
|
||||
<pitch>1.26 1.26</pitch>
|
||||
<dimension>2 2</dimension>
|
||||
<lower_left>-1.26 -1.26</lower_left>
|
||||
<universes>
|
||||
2 2
|
||||
2 5 </universes>
|
||||
</lattice>
|
||||
<surface coeffs="0.0 0.0 0.54" id="1" name="Fuel OR" type="z-cylinder"/>
|
||||
<surface coeffs="0.0 0.0 0.33" id="2" name="inner ring a" type="z-cylinder"/>
|
||||
<surface coeffs="0.0 0.0 0.45" id="3" name="inner ring b" type="z-cylinder"/>
|
||||
<surface coeffs="0.0 0.0 0.6" id="4" name="outer ring a" type="z-cylinder"/>
|
||||
<surface coeffs="0.0 0.0 0.69" id="5" name="outer ring b" type="z-cylinder"/>
|
||||
<surface coeffs="-0.0 1.0 0 0" id="6" type="plane"/>
|
||||
<surface coeffs="-0.7071067811865475 0.7071067811865476 0 0" id="7" type="plane"/>
|
||||
<surface coeffs="-1.0 6.123233995736766e-17 0 0" id="8" type="plane"/>
|
||||
<surface coeffs="-0.7071067811865476 -0.7071067811865475 0 0" id="9" type="plane"/>
|
||||
<surface coeffs="-1.2246467991473532e-16 -1.0 0 0" id="10" type="plane"/>
|
||||
<surface coeffs="0.7071067811865475 -0.7071067811865477 0 0" id="11" type="plane"/>
|
||||
<surface coeffs="1.0 -1.8369701987210297e-16 0 0" id="12" type="plane"/>
|
||||
<surface coeffs="0.7071067811865477 0.7071067811865474 0 0" id="13" type="plane"/>
|
||||
<surface boundary="reflective" coeffs="-1.26" id="14" name="minimum x" type="x-plane"/>
|
||||
<surface boundary="reflective" coeffs="1.26" id="15" name="maximum x" type="x-plane"/>
|
||||
<surface boundary="reflective" coeffs="-1.26" id="16" name="minimum y" type="y-plane"/>
|
||||
<surface boundary="reflective" coeffs="1.26" id="17" name="maximum y" type="y-plane"/>
|
||||
</geometry>
|
||||
<settings>
|
||||
<run_mode>eigenvalue</run_mode>
|
||||
<particles>100</particles>
|
||||
<batches>10</batches>
|
||||
<inactive>5</inactive>
|
||||
<energy_mode>multi-group</energy_mode>
|
||||
<random_ray>
|
||||
<distance_active>100.0</distance_active>
|
||||
<distance_inactive>20.0</distance_inactive>
|
||||
<source particle="neutron" strength="1.0" type="independent">
|
||||
<space type="box">
|
||||
<parameters>-1.26 -1.26 -1 1.26 1.26 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
<volume_normalized_flux_tallies>True</volume_normalized_flux_tallies>
|
||||
<adjoint>True</adjoint>
|
||||
</random_ray>
|
||||
</settings>
|
||||
<tallies>
|
||||
<mesh id="1">
|
||||
<dimension>2 2</dimension>
|
||||
<lower_left>-1.26 -1.26</lower_left>
|
||||
<upper_right>1.26 1.26</upper_right>
|
||||
</mesh>
|
||||
<filter id="1" type="mesh">
|
||||
<bins>1</bins>
|
||||
</filter>
|
||||
<filter id="2" type="energy">
|
||||
<bins>1e-05 0.0635 10.0 100.0 1000.0 500000.0 1000000.0 20000000.0</bins>
|
||||
</filter>
|
||||
<tally id="1" name="Mesh tally">
|
||||
<filters>1 2</filters>
|
||||
<scores>flux fission nu-fission</scores>
|
||||
<estimator>analog</estimator>
|
||||
</tally>
|
||||
</tallies>
|
||||
</model>
|
||||
171
tests/regression_tests/random_ray_adjoint_k_eff/results_true.dat
Normal file
171
tests/regression_tests/random_ray_adjoint_k_eff/results_true.dat
Normal file
|
|
@ -0,0 +1,171 @@
|
|||
k-combined:
|
||||
1.006640E+00 1.812967E-03
|
||||
tally 1:
|
||||
6.684129E+00
|
||||
8.939821E+00
|
||||
2.685967E+00
|
||||
1.443592E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
6.358774E+00
|
||||
8.091444E+00
|
||||
9.687217E-01
|
||||
1.878029E-01
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
5.963160E+00
|
||||
7.117108E+00
|
||||
1.932332E-01
|
||||
7.473914E-03
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
5.137593E+00
|
||||
5.283310E+00
|
||||
1.714616E-01
|
||||
5.884834E-03
|
||||
1.086218E-06
|
||||
2.361752E-13
|
||||
4.857253E+00
|
||||
4.719856E+00
|
||||
5.689580E-02
|
||||
6.476286E-04
|
||||
2.989356E-03
|
||||
1.787808E-06
|
||||
4.830516E+00
|
||||
4.666801E+00
|
||||
7.203015E-03
|
||||
1.037676E-05
|
||||
3.620020E+00
|
||||
2.620927E+00
|
||||
5.161382E+00
|
||||
5.328124E+00
|
||||
6.786255E-02
|
||||
9.210763E-04
|
||||
5.531943E+00
|
||||
6.120553E+00
|
||||
5.414034E+00
|
||||
5.864661E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
5.632338E+00
|
||||
6.347626E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
5.682608E+00
|
||||
6.462382E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
5.310716E+00
|
||||
5.645180E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
4.945409E+00
|
||||
4.893171E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
4.842688E+00
|
||||
4.690352E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
5.117198E+00
|
||||
5.237280E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
6.938711E+00
|
||||
9.633345E+00
|
||||
2.835258E+00
|
||||
1.608212E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
6.549505E+00
|
||||
8.584036E+00
|
||||
1.015138E+00
|
||||
2.061993E-01
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
6.050651E+00
|
||||
7.327711E+00
|
||||
1.992816E-01
|
||||
7.948424E-03
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
5.113981E+00
|
||||
5.234801E+00
|
||||
1.732323E-01
|
||||
6.006619E-03
|
||||
1.097435E-06
|
||||
2.410627E-13
|
||||
4.837033E+00
|
||||
4.680541E+00
|
||||
5.760042E-02
|
||||
6.637112E-04
|
||||
3.026377E-03
|
||||
1.832205E-06
|
||||
4.827049E+00
|
||||
4.660105E+00
|
||||
7.319913E-03
|
||||
1.071647E-05
|
||||
3.678770E+00
|
||||
2.706730E+00
|
||||
5.175337E+00
|
||||
5.356957E+00
|
||||
6.923046E-02
|
||||
9.586177E-04
|
||||
5.643451E+00
|
||||
6.370016E+00
|
||||
6.693323E+00
|
||||
8.964322E+00
|
||||
2.753307E+00
|
||||
1.516683E+00
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
6.358384E+00
|
||||
8.090233E+00
|
||||
9.912008E-01
|
||||
1.965868E-01
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
5.957484E+00
|
||||
7.103246E+00
|
||||
1.974033E-01
|
||||
7.798286E-03
|
||||
0.000000E+00
|
||||
0.000000E+00
|
||||
5.130744E+00
|
||||
5.268844E+00
|
||||
1.749233E-01
|
||||
6.123348E-03
|
||||
1.108148E-06
|
||||
2.457474E-13
|
||||
4.857340E+00
|
||||
4.720019E+00
|
||||
5.816659E-02
|
||||
6.768049E-04
|
||||
3.056125E-03
|
||||
1.868351E-06
|
||||
4.830629E+00
|
||||
4.667018E+00
|
||||
7.366289E-03
|
||||
1.085264E-05
|
||||
3.702077E+00
|
||||
2.741125E+00
|
||||
5.164864E+00
|
||||
5.335279E+00
|
||||
6.947917E-02
|
||||
9.655086E-04
|
||||
5.663725E+00
|
||||
6.415806E+00
|
||||
20
tests/regression_tests/random_ray_adjoint_k_eff/test.py
Normal file
20
tests/regression_tests/random_ray_adjoint_k_eff/test.py
Normal file
|
|
@ -0,0 +1,20 @@
|
|||
import os
|
||||
|
||||
from openmc.examples import random_ray_lattice
|
||||
|
||||
from tests.testing_harness import TolerantPyAPITestHarness
|
||||
|
||||
|
||||
class MGXSTestHarness(TolerantPyAPITestHarness):
|
||||
def _cleanup(self):
|
||||
super()._cleanup()
|
||||
f = 'mgxs.h5'
|
||||
if os.path.exists(f):
|
||||
os.remove(f)
|
||||
|
||||
|
||||
def test_random_ray_basic():
|
||||
model = random_ray_lattice()
|
||||
model.settings.random_ray['adjoint'] = True
|
||||
harness = MGXSTestHarness('statepoint.10.h5', model)
|
||||
harness.main()
|
||||
Loading…
Add table
Add a link
Reference in a new issue