def _get_depleter_decay():
dt = depletr.nuclides.half_lives.ALPHA[pu239.name]
depper = depletr.Depleter(power=1,
enrichment=0,
spectrum="thermal",
max_burnup=0)
nuclides_names = depper.get_all_nuclide_names()
nuclides_names += [
depletr.nuclides.constants.DEADEND_ACTINIDE,
depletr.nuclides.constants.FISSION_PRODUCT
]
num = len(nuclides_names)
indices = dict(zip(nuclides_names, range(num)))
q0 = np.zeros(num)
i_np239 = indices[np239.name]
q0[i_np239] = 1
i_pu238 = indices[pu238.name]
q0[i_pu238] = 1
qhist = depper.decay(q0, 1, [dt, 2 * dt])
return indices, qhist
# Questions 1-4
import depletr
import scipy as sp
SPECTRUM = "fast"
AVERAGE_KINF = {"thermal": 1.3169320996513936, "fast": 0.9892984136969714}
ELEMENTS = ("Pu", "Am", "Cm")
# found with quicksolve.py
MOX_AT = sp.array(
[0, 0.03182388222963699, 0.03319650338671934, 0.03356631994343097])
DESCRIPTOR = ("Fresh ", "Once-Burnt ", "Twice-Burnt", "Thrice-Burnt")
NSTEPS = 100
study = depletr.Depleter(power=35,
enrichment=5,
max_burnup=50,
spectrum=SPECTRUM)
all_nuclides = study.get_all_nuclides()
num_nuclides = len(all_nuclides)
cycle_wts = sp.zeros((num_nuclides + 2, len(MOX_AT)))
cout = None
for i, mox_frac in enumerate(MOX_AT):
print(DESCRIPTOR[i], "Fuel")
print("Mox fraction: {:6.3%}".format(mox_frac))
if i == 0:
# Fresh fuel
cout = study.deplete_fresh(NSTEPS, plots=0)
else:
cin = study.reprocess(cout, ELEMENTS, mox_frac)
print(100 * cin / cin.sum())
import numpy as np
import depletr
POWER = 35 # W/g
ENRICHMENT = 5 # wt% U235
BURNUP = 60 # MW-d/kg-HM
DECAY_TIMES = np.logspace(-1, 4, 6) # Years
SPECTRA = ("thermal", "fast")
# For each spectrum: Set `PLOT` to 0 for no plots,
# 1 for subplots on the same figure, or >1 for separate figures.
PLOT = 1
for spectrum in SPECTRA:
print()
header = "{} Reactor".format(spectrum.title())
header += "\n" + "-"*len(header)
print(header)
study = depletr.Depleter(POWER, ENRICHMENT, max_burnup=BURNUP, spectrum=spectrum)
print(">Depleting to {} MW-d/kg-HM:".format(BURNUP))
spent_fuel = study.deplete_fresh(nsteps=1000, plots=PLOT)
print("\n>Decaying in spent fuel pool for {} years".format(int(DECAY_TIMES.max())))
times_in_seconds = DECAY_TIMES*depletr.nuclides.half_lives.YEAR
respository = study.decay(spent_fuel, nsteps=1000, times=times_in_seconds)
nuclide_names = study.get_all_nuclide_names()
# new
respository /= respository.sum()
depletr.printer.print_decay_results(nuclide_names, DECAY_TIMES, respository)
if PLOT:
study.show()
# 22.215, PSet02 # by Travis Labossiere-Hickman (email: [email protected]) # # Question 5 import depletr from scipy.constants import N_A AVG_MASS = 239 MEV_PER_FISSION = 200 MEV_PER_MWD = 5.39266E23 NHM = 1000*N_A/AVG_MASS X = MEV_PER_FISSION/MEV_PER_MWD BU = 0.15*NHM*X ELEMENTS = ("Pu", "Am", "Cm") NSTEPS = 500 # PWR with fresh fuel thermal_deplet = depletr.Depleter(power=35, enrichment=5, max_burnup=50, spectrum="thermal") cout = thermal_deplet.deplete_fresh(NSTEPS, plots=0, verbose=False) # Fast reactor with once-burnt fuel cin = thermal_deplet.reprocess(cout, ELEMENTS, mox_frac=0.3) fast_deplet = depletr.Depleter(power=35, enrichment=-0.71, max_burnup=BU, spectrum="fast") cout = fast_deplet.reload(cin, NSTEPS) print(cout)