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openmc-designs/BEAVRS/make_beavrs.py

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#!/usr/bin/env python3
import numpy as np
import openmc.deplete
from beavrs.builder import BEAVRS
import argparse, json, openmc, os, shutil, sys
import matplotlib.pyplot as plt
try:
from mpi4py import MPI
except ModuleNotFoundError:
print("Cannot use MPI")
try:
comm = MPI.COMM_WORLD
rank = comm.Get_rank()
except NameError:
comm = None
rank = 0
parser = argparse.ArgumentParser(description="Program to make BEAVRS reactor and run" \
" simulations with resulting geometry")
parser.add_argument('-d', '--2d', action='store_true', dest='is_2d',
default=False, help='Create 2D BEAVRS input files, 3D by default')
parser.add_argument('-s', '--symmetric', action='store_true', dest='is_symmetric',
default=False, help='Create octant-symmetric input files, not symmetric by default')
parser.add_argument('-e', '--deplete', action='store_true', dest='run_deplete', default=False,
help='Run the depletion code for this setup')
parser.add_argument('-i', '--insert', action='store', type=int, dest='rod_loc', default=200,
help='Set where the control rods should be. Acceptable values are 15-573')
parser.add_argument('-o', '--optimal', action='store_true', default=False,
help='Find the best combination of particles, inactive and active batches to run')
parser.add_argument('-r', '--run', action='store_true', default=False,
help='Run the model once after building it')
parser.add_argument('--shutdown', action='store_true', default=False,
help='Set reactor to be in shutdown, all control rods fully inserted.')
args = parser.parse_args()
if rank == 0:
try:
os.mkdir(os.path.dirname(os.path.realpath(__file__)) + '/build')
except OSError: pass
comm.Barrier()
os.chdir(os.path.dirname(os.path.realpath(__file__)) + '/build')
def no_overwrite(rank, filename):
if os.path.isfile(filename) and rank == 0:
j = 0
new_filepath = filename*1
path, new_name = os.path.split(new_filepath)
name_len = len(new_name)
while os.path.isfile(new_filepath):
if new_name[-2] == 'h':
new_name = f'#{new_name}.{j}'
else:
j += 1
new_name = f'{new_name[:name_len+1]}.{j}'
new_filepath = f"{path}/{new_name}"
print(f"Backed up file {filename} to {new_filepath}")
os.replace(filename, new_filepath)
comm.Barrier()
def run_loop(rank, val):
b.set_S(rank, val)
return b.export_model()
if args.shutdown:
b = BEAVRS(rank, 573, 228, is_symmetric=args.is_symmetric, is_2d=args.is_2d)
else:
b = BEAVRS(rank, args.rod_loc, 0, is_symmetric=args.is_symmetric, is_2d=args.is_2d)
# openmc.calculate_volumes()
# openmc.plot_geometry()
if args.optimal:
particles = [5000, 10000, 20000, 50000, 100000]
inactive = [10, 20, 50, 100, 150]
active = [50, 100, 150, 300, 500]
for p in particles:
for i in inactive:
for a in active:
if rank == 0:
print(f"Particles: {p} Inactive Cycles: {i} Active Cycles: {a}\n\n")
b.set_params(batches=i+a,inactive=i,particles=p)
b.export_xml(rank)
openmc.run()
if rank == 0:
print("\n\n\n")
sys.stdout.flush()
###############################################################################
# Depletion Settings
###############################################################################
elif args.run_deplete:
b.set_params(batches=350,inactive=50,particles=20000)
b.set_full_depletion_mats()
# b.set_fuel_otf_files()
# b.set_distributed_materials()
# b.set_fuel_distrib_tallies()
# b.set_fuel_depletion_tallies()
## Get fission Q values from JSON file generated by get_fission_qvals.py
with open('../beavrs/serpent_fissq.json', 'r') as f:
serpent_fission_q = json.load(f)
chain_file = "/opt/xdata/endfb-vii.1-hdf5/chain_endfb71_pwr.xml"
if rank == 0:
try:
os.makedirs('depletion_results')
except FileExistsError:
pass
## setting the system linear power [W]
"""powers = [45.50,91.01,136.51,182.02,227.52,273.03,324.45,324.45,273.03,273.03,227.52,182.02,136.51,91.01,45.50]
time_steps = [8640.00,8640.00,8640.00,8640.00,8640.00,8640.00,4268160.00,45792000.00,1728000.00,46915200.00,8640.00,8640.00,8640.00,8640.00,8640.00]"""
## cumulative steps in days
# time_steps_cum = np.array([3/24, 6/24, 9/24, 12/24, 15/24, 18/24, 21/24, 1, 10, 30, 60, 90, 365, 548])
# i = 298 300 300 300 300 300 300 300 300 300 300 300 300 300
time_steps_cum = np.array([12/24, 24/24, 36/24, 48/24, 60/24, 72/24, 84/24, 4, 10, 30, 60, 90, 365, 548])
time_steps = np.diff(time_steps_cum, prepend=0.0)
## Power in Watts
full_power = 3411e6
powers = [full_power if x > 4 else full_power*x/4 for x in time_steps_cum]
## setting the transport operator
model = b.export_model()
comm.Barrier()
# openmc.plot_geometry()
operator = openmc.deplete.CoupledOperator(model, chain_file,
#diff_burnable_mats=False, normalization_mode='fission-q',
fission_q=serpent_fission_q, fission_yield_mode="average")
## depleting using a first-order predictor algorithm
## Working algorithms: CELI, CECM, SILEQI
integrator = openmc.deplete.SILEQIIntegrator(operator, time_steps, powers, timestep_units='d')
integrator.integrate()
"""
if rank == 0:
print(time_steps)
i = 0
for power, time_step in zip(powers, time_steps):
if rank == 0:
print(f'Current loop info: {power} {time_step}')
## setting the transport operator
model = b.export_model()
comm.Barrier()
openmc.plot_geometry()
operator = openmc.deplete.CoupledOperator(model, chain_file,
#diff_burnable_mats=False, normalization_mode='fission-q',
fission_q=serpent_fission_q, fission_yield_mode="average")
## depleting using a first-order predictor algorithm
## Working algorithms: CELI, CECM, SILEQI
integrator = openmc.deplete.SILEQIIntegrator(operator, time_steps, powers, timestep_units='d')
integrator.integrate()
filename = f'depletion_results/depletion_results_t{i}.h5'
no_overwrite(rank, filename)
os.replace('depletion_results.h5', filename)
shutil.copy2('materials.xml', f'depletion_results/materials_{i}.xml')
i += 1
"""
results = openmc.deplete.Results('depletion_results.h5')
# Get materials at the end of the last simulation
if rank == 0:
model.materials = results.export_to_materials(len(time_steps))
model.export_to_xml()
comm.Barrier()
# Obtain K_eff as a function of time
time, keff = results.get_keff(time_units='d')
n_U235 = 0
Xe_capture = 0
n_Xe135 = 0
tmp = [[],[],[]]
# ['Fuel 1.6%' 'Fuel 2.4%' 'Fuel 3.1%' 'Fuel 3.2%' 'Fuel 3.4%']
for mat in b.mats:
# Obtain U235 concentration as a function of time
_, tmp[0] = results.get_atoms(mat, 'U235')
# Obtain Xe135 capture reaction rate as a function of time
_, tmp[1] = results.get_reaction_rate(mat, 'Xe135', '(n,gamma)')
# Obtain U235 concentration as a function of time
_, tmp[2] = results.get_atoms(mat, 'Xe135')
n_U235 += tmp[0]
Xe_capture += tmp[1]
n_Xe135 += tmp[2]
#######################################################################
# Generate plots
#######################################################################
fig, ax = plt.subplots()
ax.errorbar(time,keff[:,0], keff[:,1], label="k-effective")
ax.set_xlabel("Time [d]")
ax.set_ylabel("Keff")
if rank == 0:
plt.savefig("k-effective.png", dpi=150)
plt.draw()
fig, ax = plt.subplots()
ax.plot(time, n_U235, label="U235")
ax.set_xlabel("Time [d]")
ax.set_ylabel("U235 atoms")
if rank == 0:
plt.savefig("U235", dpi=150)
plt.draw()
fig, ax = plt.subplots()
ax.plot(time, Xe_capture, label="Xe135 capture")
ax.set_xlabel("Time [d]")
ax.set_ylabel("Xe135 capture rate")
if rank == 0:
plt.savefig("Xe135_capture", dpi=150)
plt.draw()
fig, ax = plt.subplots()
ax.plot(time, n_Xe135, label="Xe135")
ax.set_xlabel("Time [d]")
ax.set_ylabel("Xe135 atoms")
if rank == 0:
plt.savefig("Xe135", dpi=150)
plt.draw()
elif args.run:
b.set_params(batches=350,inactive=50,particles=20000)
"""rod_loc, guess_list, result = openmc.search_for_keff(run_loop, initial_guess=10, target=1.0,
tol=6e-4, print_iterations=True, run_args=(rank))"""
b.export_xml(rank)
openmc.run()
else:
b.set_params(batches=350,inactive=50,particles=20000)
b.export_xml(rank)
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