def testAtten(self):
print("\n========= INITIATING BEAM TEST ==========")
width, dX = 50.0, 0.4
sNord = 8
attnMat = mx.mixedMat({'c12': 1.0})
attnMat.setDensity(2.24)
print(attnMat.nDdict)
mesh1D = sn.Mesh1Dsn([0, width], dX, attnMat, sN=sNord)
# define fixed boundary cond
srcStrength = 1.e6 # [n / cm**2-s]
# energy distribution of source (all born at 0.1MeV
srcEnergy = np.array([1.0, 0, 0.0, 0, 0, 0, 0, 0, 0, 0])
bcs = {0: {'fixN': (1, [srcStrength, srcEnergy])},
-1: {'vac': (2, 0)}}
mesh1D.setBCs(bcs)
for si in range(1):
resid = mesh1D.sweepMesh(1)
if resid < 1e-5:
break
scalarFlux = mesh1D.getScalarFlux()
for g in range(len(srcEnergy)):
sfp.plot1DScalarFlux(scalarFlux[:][:, g], np.arange(0, width, dX), label='Group ' + str(g + 1))
sfp.plot1DNeutronND(scalarFlux[:][:, g], np.arange(0, width, dX), g)
flxPlt.plotFluxE(scalarFlux[-1][::-1]) # flux vs E at left edge
# plot ord fluxes at leading edge
ordFlux = mesh1D.getOrdFlux()
angles = np.arccos(mesh1D.cells[0].sNmu)
g = 2
mag = ordFlux[1][g, 0, :] / sum(ordFlux[1][g, 0, :])
pof.compass(angles, mag, figName='polar_grp3')
# plot ord fluxes at mid plane
g = 3
mag = ordFlux[1][g, 0, :] / sum(ordFlux[1][g, 0, :])
pof.compass(angles, mag, figName='polar_grp4')
def testKeigenSweep(self):
print("\n========= INITIATING K-EIGEN TEST ==========")
width, dX = 4.0, 0.05
mesh1D = sn.Mesh1Dsn([0, width], dX, pinMaterial, sN=8)
#bcs = {0: {'vac': (1, 0)}, -1: {'vac': (2, 0)}} # vac bc test
bcs = {0: {'ref': (1, 0)}, -1: {'ref': (2, 0)}} # ref bc test
mesh1D.setBCs(bcs)
#
fissionSrc = []
mesh1D.setKeff(1.)
fissionSrc.append(np.sum(mesh1D.fissionSrc())) # todo mult by width
scalarFlux = mesh1D.getScalarFlux()
sfp.plot1DScalarFlux(scalarFlux[:][:, 1], np.arange(0, width, dX))
for pI in range(8):
# Perform source iterations
nSourceIterations = 80
for si in range(nSourceIterations):
mesh1D.sweepMesh(10)
fissionSrc.append(np.sum(mesh1D.fissionSrc()))
knew = mesh1D.keff * (fissionSrc[-1] / fissionSrc[-2])
print("Outter iteration: " + str(pI) + " k-eff :" + str(knew))
scalarFlux = mesh1D.getScalarFlux()
flxPlt.plotFluxE(scalarFlux[len(np.arange(0, width, dX)) /
2][::-1])
sfp.plot1DScalarFlux(scalarFlux[:][:, 1], np.arange(0, width, dX))
mesh1D.setKeff(knew)
mesh1D.postSI()
def testKeigenSweep(self):
print("\n========= INITIATING K-EIGEN TEST ==========")
width, dX = 4.0, 0.05
mesh1D = sn.Mesh1Dsn([0, width], dX, pinMaterial, sN=8)
#bcs = {0: {'vac': (1, 0)}, -1: {'vac': (2, 0)}} # vac bc test
bcs = {0: {'ref': (1, 0)}, -1: {'ref': (2, 0)}} # ref bc test
mesh1D.setBCs(bcs)
#
fissionSrc = []
mesh1D.setKeff(1.)
fissionSrc.append(np.sum(mesh1D.fissionSrc())) # todo mult by width
scalarFlux = mesh1D.getScalarFlux()
sfp.plot1DScalarFlux(scalarFlux[:][:, 1], np.arange(0, width, dX))
for pI in range(8):
# Perform source iterations
nSourceIterations = 80
for si in range(nSourceIterations):
mesh1D.sweepMesh(10)
fissionSrc.append(np.sum(mesh1D.fissionSrc()))
knew = mesh1D.keff * (fissionSrc[-1] / fissionSrc[-2])
print("Outter iteration: " + str(pI) + " k-eff :" + str(knew))
scalarFlux = mesh1D.getScalarFlux()
flxPlt.plotFluxE(scalarFlux[len(np.arange(0, width, dX)) / 2][::-1])
sfp.plot1DScalarFlux(scalarFlux[:][:, 1], np.arange(0, width, dX))
mesh1D.setKeff(knew)
mesh1D.postSI()
def testAtten(self):
print("\n========= INITIATING MULT REGION BEAM TEST ==========")
sNord = 18
# define fixed source boundary cond
srcStrength = 1.e6 # [n / cm**2-s]
# energy distribution of source (all born at 0.1MeV
srcEnergy = np.array([1.0, 0, 0.0, 0, 0, 0, 0, 0, 0, 0])
#
# ## REGION 1 - GRAPHITE ###
width1, dX1 = 25.0, 1.0
region1Mat = mx.mixedMat({'c12': 1.0})
region1Mat.setDensity(1.96)
region1mesh1D = sn.Mesh1Dsn([0, width1], dX1, region1Mat, sN=sNord)
bcs1 = {0: {'fixN': (1, [srcStrength, srcEnergy])}}
region1mesh1D.setBCs(bcs1)
# ## REGION 2 - BORATED CARBON ###
width2, dX2 = 25.0, 0.05
region2Mat = mx.mixedMat({'c12': 0.99, 'b10': 0.01})
region2Mat.setDensity(1.9)
region2mesh1D = sn.Mesh1Dsn([width1 + dX1 / 2. + dX2 / 2., width1 + dX1 / 2. + dX2 / 2. + width2], dX2, region2Mat, sN=sNord)
bcs2 = {-1: {'vac': (2, 0)}}
region2mesh1D.setBCs(bcs2)
#
# ## BUILD DOMAIN ###
domain = sn.SubDomain()
domain.addRegion(region1mesh1D)
domain.addRegion(region2mesh1D)
domain.buildSweepTree()
#
# ## SWEEP DOMAIN ###
for si in range(180):
resid = domain.sweepSubDomain(1)
if resid < 1e-5:
break
scalarFlux = domain.getScalarFlux()
for g in range(len(srcEnergy)):
pass
flxPlt.plotFluxE(scalarFlux[-1][::-1]) # flux vs E at left edge
centroids = [cell.centroid for cell in domain.regions[0].cells]
centroids += [cell.centroid for cell in domain.regions[1].cells]
for g in range(len(srcEnergy)):
sfp.plot1DScalarFlux(scalarFlux[:][:, g], centroids, label='Group ' + str(g + 1))
# sfp.plot1DNeutronND(scalarFlux[:][:, g], centroids, g)
# plot ord fluxes at leading edge
ordFlux = domain.getOrdFlux()
angles = np.arccos(domain.regions[0].cells[0].sNmu)
g = 2
mag = ordFlux[1][g, 0, :] / sum(ordFlux[1][g, 0, :])
pof.compass(angles, mag, figName='polar_grp3')
# plot ord fluxes at mid plane
g = 3
mag = ordFlux[1][g, 0, :] / sum(ordFlux[1][g, 0, :])
pof.compass(angles, mag, figName='polar_grp4')
def testAtten(self):
print("\n========= INITIATING BEAM TEST ==========")
width, dX = 50.0, 0.4
sNord = 8
attnMat = mx.mixedMat({'c12': 1.0})
attnMat.setDensity(2.24)
print(attnMat.nDdict)
mesh1D = sn.Mesh1Dsn([0, width], dX, attnMat, sN=sNord)
# define fixed boundary cond
srcStrength = 1.e6 # [n / cm**2-s]
# energy distribution of source (all born at 0.1MeV
srcEnergy = np.array([1.0, 0, 0.0, 0, 0, 0, 0, 0, 0, 0])
bcs = {0: {'fixN': (1, [srcStrength, srcEnergy])}, -1: {'vac': (2, 0)}}
mesh1D.setBCs(bcs)
for si in range(1):
resid = mesh1D.sweepMesh(1)
if resid < 1e-5:
break
scalarFlux = mesh1D.getScalarFlux()
for g in range(len(srcEnergy)):
sfp.plot1DScalarFlux(scalarFlux[:][:, g],
np.arange(0, width, dX),
label='Group ' + str(g + 1))
sfp.plot1DNeutronND(scalarFlux[:][:, g], np.arange(0, width, dX),
g)
flxPlt.plotFluxE(scalarFlux[-1][::-1]) # flux vs E at left edge
# plot ord fluxes at leading edge
ordFlux = mesh1D.getOrdFlux()
angles = np.arccos(mesh1D.cells[0].sNmu)
g = 2
mag = ordFlux[1][g, 0, :] / sum(ordFlux[1][g, 0, :])
pof.compass(angles, mag, figName='polar_grp3')
# plot ord fluxes at mid plane
g = 3
mag = ordFlux[1][g, 0, :] / sum(ordFlux[1][g, 0, :])
pof.compass(angles, mag, figName='polar_grp4')
# Load xs database
import materials.materialMixxer as mx
import utils.pinCellMatCalc as pcm
mx.genMaterialDict('./materials/newXS')
# Create pin cell material
pinCellMaterial = pcm.createPinCellMat()
modDict = {'u235': False, 'u238': False, 'zr90': False}
resDict = {'h1': False, 'o16': False, 'zr90': False}
ssPinCellMaterial = pinCellMaterial.selfSheild(modDict, resDict)
# ssPinCellMaterial = pinCellMaterial.selfSheild()
# Solve k-eigenvalue problem
kVec, fluxVec = solveCrit(ssPinCellMaterial, k0=1.1)
# Print f-factors for u238 and u235
print(ssPinCellMaterial.microDat['u235']['f'])
print(ssPinCellMaterial.microDat['u238']['f'])
# Compute U235 and U238 reaction rates
# numberDensity235 = pinCellMaterial.nDdict['u235']
# numberDensity238 = pinCellMaterial.nDdict['u238']
# u235 = mx.mixedMat({'u235': numberDensity235})
# u238 = mx.mixedMat({'u238': numberDensity238})
# Ru238 = np.sum(u238.macroProp['Nnufission'] * fluxVec[-1])
# Ru235 = np.sum(u235.macroProp['Nnufission'] * fluxVec[-1])
# fRR = np.sum([Ru238, Ru235])
# print("Relative U238 fission reaction rate: " + str(Ru238 / fRR))
# print("Relative U235 fission reaction rate: " + str(Ru235 / fRR))
# plot results
import plotters.fluxEplot as flxPlt
flxPlt.plotFluxE(fluxVec[-1][::-1], label='Self Shield ON')
kVec, fluxVec = solveCrit(pinCellMaterial, k0=1.1)
flxPlt.plotFluxE(fluxVec[-1][::-1], label='Self Shield OFF')
